Conference Articles of the Laboratory for Reactor Physics and Thermal-Hydraulics

Every year, several important international and national conferences and meetings take place. Our scientists, post docs and students are regularly invited to take part, write a conference paper and have presentations.

Please find here a selection of conferences:

PHYSOR - International Conference on Physics of Reactors
NURETH - International Topical Meeting on Nuclear Reactor Thermalhydraulics
M&C - International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering
ICONE - International Conference of Nuclear Engineering
TOP FUEL - Light Wather Reactor Fuel Performance Conference
ANS Student Conference
ENYGF - European Nuclear Young Generation Forum

2024

Migliorini M, Zachos PK, Macmanus DG, Doll U, Dues M, Steinbock J, et al.
Seeding-free inlet flow distortion measurements using filtered Rayleigh scattering: integration in a complex intake test facility
In: AIAA SciTech forum and exposition, 2024. Reston: American Institute of Aeronautics and Astronautics; 2024:AIAA 2024-2831 (17 pp.). https://doi.org/10.2514/6.2024-2831
DORA PSI
Ramos Perez A, Lind T, Petrov V, Manera A, Prasser HM
Aerosol retention measurements with Wire-mesh sensors: an experimental and computational approach
In: SWINTH-2024: Specialist workshop on advanced instrumentation and measurement techniques for nuclear reactor thermal hydraulics and severe accidents. Dresden: K.I.T. Group; 2024:002 (14 pp.).
DORA PSI
Tagliente G, Aberle O, Alcayne V, Amaducci S, Andrzejewski J, Babiano-Suarez V, et al.
The n_TOF facility at CERN
In: Cerutti F, Kawano T, Marin S, Pujol F, Talou P, eds. 16th Varenna conference on nuclear reaction mechanisms (NRM2023). Vol. 292. EPJ web conferences. Les Ulis Cedex A: EDP Sciences; 2024:12002 (8 pp.). https://doi.org/10.1051/epjconf/202429212002
DORA PSI

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2023

Ahn T, Petrov V, Manera A
Comparison between high-resolution gamma-ray tomography and wire-mesh sensor for air-water flow in a rod bundle geometry
In: 20th international topical meeting on nuclear reactor thermal hydraulics (NURETH-20). Illinois: American Nuclear Society; 2023:2196-2209. https://doi.org/10.13182/NURETH20-40846
DORA PSI
Al-Yahia OS, Bernard M, Clifford I, Perret G, Bajorek S, Ferroukhi H
Implementation of a three-field framework in TRACE to improve the prediction of reactor core reflood conditions part II
In: 20th international topical meeting on nuclear reactor thermal hydraulics (NURETH-20). Illinois: American Nuclear Society; 2023:110-122. https://doi.org/10.13182/NURETH20-40133
DORA PSI
Alcayne V, Cano-Ott D, Garcia J, González-Romero E, Martínez T, Mendoza E, et al.
A segmented total energy detector (sTED) for (n, γ) cross section measurements at n_TOF EAR2
In: Mattoon CM, Vogt R, Escher J, Thompson I, eds. 15th international conference on nuclear data for science and technology (ND2022). Vol. 284. EPJ web conferences. Les Ulis Cedex A: EDP Sciences; 2023:01043 (5 pp.). https://doi.org/10.1051/epjconf/202328401043
DORA PSI
Alcayne V, Mendoza E, Cano-Ott D, Kimura A, Aberle O, Amaducci S, et al.
Results of the ²⁴⁴Cm, ²⁴⁶Cm and ²⁴⁸Cm neutron-induced capture cross sections measurements at EAR1 and EAR2 of the n_TOF facility
In: Mattoon CM, Vogt R, Escher J, Thompson I, eds. 15th international conference on nuclear data for science and technology (ND2022). Vol. 284. EPJ web conferences. Les Ulis Cedex A: EDP Sciences; 2023:01009 (6 pp.). https://doi.org/10.1051/epjconf/202328401009
DORA PSI
Babiano-Suarez V, Balibrea-Correa J, Caballero-Ontanaya L, Domingo-Pardo C, Ladarescu I, Lerendegui-Marco J, et al.
High resolution ⁸⁰Se(n,γ) cross section measurement at CERN n_TOF
In: Mattoon CM, Vogt R, Escher J, Thompson I, eds. 15th international conference on nuclear data for science and technology (ND2022). Vol. 284. EPJ web conferences. Les Ulis Cedex A: EDP Sciences; 2023:01001 (6 pp.). https://doi.org/10.1051/epjconf/202328401001
DORA PSI
Cabellos O, Hursin M, Palmiotti P
WPEC/SG46 exercise on target accuracy requirement
In: Mattoon CM, Vogt R, Escher J, Thompson I, eds. 15th international conference on nuclear data for science and technology (ND2022). Vol. 284. EPJ web conferences. Les Ulis Cedex A: EDP Sciences; 2023:14012 (4 pp.). https://doi.org/10.1051/epjconf/202328414012
DORA PSI
Chae M-S, Paladino D, Kelm S
Analyses of jet-buoyant flow in a multi-compartment containment using an open-source solver
In: 20th international topical meeting on nuclear reactor thermal hydraulics (NURETH-20). Illinois: American Nuclear Society; 2023:4059-4072. https://doi.org/10.13182/NURETH20-40154
DORA PSI
Clifford I, Kral P, Vyskocil L, Pistora V, Trewin R, Filonova Y, et al.
State of the art for thermal-hydraulic analysis of pressurised thermal shock scenarios
In: 20th international topical meeting on nuclear reactor thermal hydraulics (NURETH-20). Illinois: American Nuclear Society; 2023:5778-5790. https://doi.org/10.13182/NURETH20-40247
DORA PSI
Clifford I, Al-Yahia OS, Ferroukhi H
TRACE investigation on the performance of passive safety condenser as ultimate heat sink
In: Proceedings of Saudi international conference on nuclear power engineering (SCOPE). sine loco: SCOPE; 2023:23220 (6 pp.).
DORA PSI
Dehbi A, Kapulla R
CFD simulations of large-scale tests highlighting the effects of thermal radiation in steam-containing atmospheres
Presented at:
DORA PSI
Doll U, Kapulla R, Steinbock J, Dues M, Migliorini M, Zachos PK
Seeding-free inlet flow distortion measurement by filtered Rayleigh scattering: diagnostic approach and verification
In: AIAA SCITECH 2023 forum. Reston: American Institute of Aeronautics and Astronautics; 2023:714-725. https://doi.org/10.2514/6.2023-1372
DORA PSI
Domingo-Pardo C, Babiano-Suarez V, Balibrea-Correa J, Caballero L, Ladarescu I, Lerendegui-Marco J, et al.
Compton imaging for enhanced sensitivity (n,γ) cross section TOF experiments: status and prospects
In: Mattoon CM, Vogt R, Escher J, Thompson I, Žugec P, eds. 15th international conference on nuclear data for science and technology (ND2022). Vol. 284. EPJ web conferences. Les Ulis Cedex A: EDP Sciences; 2023:01018 (5 pp.). https://doi.org/10.1051/epjconf/202328401018
DORA PSI
Domingo-Pardo C, Aberle O, Alcayne V, Altieri S, Amaducci S, Andrzejewski J, et al.
The neutron time-of-flight facility n_TOF at CERN: recent facility upgrades and detector developments
In: 28th international nuclear physics conference (INPC 2022). Vol. 2586. Journal of physics: conference series. Bristol: IOP Publishing; 2023:012150 (11 pp.). https://doi.org/10.1088/1742-6596/2586/1/012150
DORA PSI
Dupont E, Otuka N, Rochman D, Nogèure G, Aberle O, Alcayne V, et al.
Overview of the dissemination of n_TOF experimental data and resonance parameters
In: Mattoon CM, Vogt R, Escher J, Thompson I, eds. 15th international conference on nuclear data for science and technology (ND2022). Vol. 284. EPJ web conferences. Les Ulis Cedex A: EDP Sciences; 2023:18001 (4 pp.). https://doi.org/10.1051/epjconf/202328418001
DORA PSI
Espegren F, Suckow D, Lind T, Mantzaras J, Theile J
Methyl iodide retention in Ag-Zeolite material under filtered containment venting system condition
In: 20th international topical meeting on nuclear reactor thermal hydraulics (NURETH-20). Illinois: American Nuclear Society; 2023:3759-3771. https://doi.org/10.13182/NURETH20-40735
DORA PSI
Faldella F, Eisenring S, Kim T, Doll U, Jansohn P
Turbulent flame speed and flame characteristics of lean premixed H₂-CH₄ flames at moderate pressure levels
In: Proceedings of ASME Turbo Expo 2023: turbomachinery technical conference and exposition. Vol. 3A. Turbo expo: power for land, sea and air. New York: American Society of Mechanical Engineers ASME; 2023:V03AT04A068 (10 pp.). https://doi.org/10.1115/gt2023-102527
DORA PSI
Fogliatto E, Clifford I
CFD simulations of the UPTF-TRAM test C1
In: 20th international topical meeting on nuclear reactor thermal hydraulics (NURETH-20). Illinois: American Nuclear Society; 2023:606-617. https://doi.org/10.13182/NURETH20-40211
DORA PSI
Freixa J, Martínez-Quiroga V, Perret G
Assessment of the choked flow model of RELAP5 for the application of inverse quantification methods
In: 20th international topical meeting on nuclear reactor thermal hydraulics (NURETH-20). Illinois: American Nuclear Society; 2023:5426-5439. https://doi.org/10.13182/NURETH20-40674
DORA PSI
García-Infantes ME, Praena P, Casanovas P, Mastromarco M, Aberle M, Alcayne M, et al.
First high resolution measurement of neutron capture resonances in ¹⁷⁶Yb at the n_TOF CERN facility
In: Mattoon CM, Vogt R, Escher J, Thompson I, eds. 15th international conference on nuclear data for science and technology (ND2022). Vol. 284. EPJ web conferences. Les Ulis Cedex A: EDP Sciences; 2023:09001 (5 pp.). https://doi.org/10.1051/epjconf/202328409001
DORA PSI
Grasso M, Petrov V, Manera A, Rivera Y
Experimental velocity profile reconstruction in thin water films
In: 20th international topical meeting on nuclear reactor thermal hydraulics (NURETH-20). ; 2023:1516-1529. https://doi.org/10.13182/NURETH20-40771
DORA PSI
Huang P-H, Ahn T, Manera A, Petrov V
Experimental study on the start-up characteristics and performance of a ten sodium heat pipe bundle array
In: 20th international topical meeting on nuclear reactor thermal hydraulics (NURETH-20). Illinois: American Nuclear Society; 2023:3479-3492. https://doi.org/10.13182/NURETH20-40775
DORA PSI
Huxford A, Coppo Leite V, Merzari E, Zou L, Petrov V
Validation of SAM-NekRS coupling against the TALL-3D STH/CFD coupling benchmark transient
In: 20th international topical meeting on nuclear reactor thermal hydraulics (NURETH-20). Illinois: American Nuclear Society; 2023:518-529. https://doi.org/10.13182/NURETH20-40528
DORA PSI
Ishikawa Y, Endo K, Narabayashi T, Suckow D, Espegren F, Lind T, et al.
Advanced FCVS system using silver zeolite AgX, AgR and XeA
In: 20th international topical meeting on nuclear reactor thermal hydraulics (NURETH-20). Illinois: American Nuclear Society; 2023:4248-4255. https://doi.org/10.13182/NURETH20-40634
DORA PSI
Ishikawa Y, Endo K, Kobayashi T, Narabayashi T, Kawahara Y, Suckow DJ
Advanced radioactive material removal system using silver zeolite (3) filtered containment venting system (FCVS) hydrogen measures
In: Proceedings of the 2023 30th international conference on nuclear engineering ICONE30. Vol. 30. sine loco: Japan Society of Mechanical Engineers; 2023:1-3. https://doi.org/10.1299/jsmeicone.2023.30.1620
DORA PSI
Kim T, Doll U, Faldella F, Jansohn P
Quantification of mixing quality effects on flashback limits for H2-rich fuel gases
In: Proceedings of ASME turbo expo 2023: turbomachinery technical conference and exposition (GT2023). Vol. 3A. Proceedings of the ASME turbo expo. New York: American Society of Mechanical Engineers ASME; 2023:(9 pp.). https://doi.org/10.1115/gt2023-101551
DORA PSI
Lerendegui-Marco J, Casanovas A, Alcayne V, Aberle O, Altieri S, Amaducci S, et al.
New perspectives for neutron capture measurements in the upgraded CERN-n_TOF Facility
In: Mattoon CM, Vogt R, Escher J, Thompson I, eds. 15th international conference on nuclear data for science and technology (ND2022). Vol. 284. EPJ web conferences. Les Ulis Cedex A: EDP Sciences; 2023:01028 (6 pp.). https://doi.org/10.1051/epjconf/202328401028
DORA PSI
Lind T, Kalilainen J, Marchetto C, Beck S, Nakamura K, Kino C, et al.
OECD/NEA ARC-F project: summary of fission product transport
In: 20th international topical meeting on nuclear reactor thermal hydraulics (NURETH-20). Illinois: American Nuclear Society; 2023:4796-4809. https://doi.org/10.13182/NURETH20-40120
DORA PSI
Malicki M, Darnowski P, Lind T
The iPWR MELCOR 2.2 parametric sensitivity analysis
In: 20th international topical meeting on nuclear reactor thermal hydraulics (NURETH-20). Illinois: American Nuclear Society; 2023:4220-4233. https://doi.org/10.13182/NURETH20-40213
DORA PSI
Manna A, Pirovano E, Colonna N, Castelluccio D, Console Camprini P, Cosentino L, et al.
Characterization of a detector setup for the measurement of the ²³⁵U(n,f) cross section relative to n-p scattering up to 500 MeV at the n_TOF facility at CERN
In: Mattoon CM, Vogt R, Escher J, Thompson I, eds. 15th international conference on nuclear data for science and technology (ND2022). Vol. 284. EPJ web conferences. Les Ulis Cedex A: EDP Sciences; 2023:04016 (5 pp.). https://doi.org/10.1051/epjconf/202328404016
DORA PSI
Mantzaras J, Arumugan VK, Theile J, Suckow D, Espegren F, Lind T
Recombination of hydrogen and carbon monoxide on silver-based zeolites in the presence of steam and at pressures up to 3 bar
In: 20th international topical meeting on nuclear reactor thermal hydraulics (NURETH-20). Illinois: American Nuclear Society; 2023:4020-4033. https://doi.org/10.13182/NURETH20-40692
DORA PSI
Mao J, Petrov V, Manera A
High-resolution experiments for mixing in large enclosures
In: 20th international topical meeting on nuclear reactor thermal hydraulics (NURETH-20). Illinois: American Nuclear Society; 2023:2152-2165. https://doi.org/10.13182/NURETH20-40559
DORA PSI
Maruyama Y, Sugiyama T, Shimada A, Lind T, Bentaib A, Sogalla M, et al.
Main outputs from the OECD/NEA ARC-F project
In: 20th international topical meeting on nuclear reactor thermal hydraulics (NURETH-20). Illinois: American Nuclear Society; 2023:4782-4795. https://doi.org/10.13182/NURETH20-40302
DORA PSI
Massimi C, Aberle O, Alcayne V, Altieri S, Amaducci S, Andrzejewski J, et al.
Neutron-induced cross section measurements
In: Freeman S, Lederer-Woods C, Manna A, Mengoni A, eds. Nuclear physics in astrophysics – X (NPA-X 2022). Vol. 279. EPJ web conferences. Les Ulis Cedex A: EDP Sciences; 2023:11009 (6 pp.). https://doi.org/10.1051/epjconf/202327911009
DORA PSI
Mastromarco M, Manna A, García-Infantes F, Amaducci S, Mengoni A, Massimi C, et al.
Measurement of the ¹⁶⁰Gd(n, γ) cross section at n_TOF and its medical implications
In: Mattoon CM, Vogt R, Escher J, Thompson I, eds. 15th international conference on nuclear data for science and technology (ND2022). Vol. 284. EPJ web conferences. Les Ulis Cedex A: EDP Sciences; 2023:09002 (5 pp.). https://doi.org/10.1051/epjconf/202328409002
DORA PSI
Michalopoulou V, Diakaki M, Vlastou R, Kokkoris M, Stamatopoulos A, Tsinganis A, et al.
Measurement of the ²³⁵U(n,f) cross section relative to the ¹⁰B(n,α) reaction with micromegas detectors at the CERN n_TOF facility: first results
In: Mattoon CM, Vogt R, Escher J, Thompson I, eds. 15th international conference on nuclear data for science and technology (ND2022). Vol. 284. EPJ web conferences. Les Ulis Cedex A: EDP Sciences; 2023:01030 (4 pp.). https://doi.org/10.1051/epjconf/202328401030
DORA PSI
Mucciola R, Paradela C, Manna A, Alaerts G, Massimi C, Kopecky S, et al.
Neutron capture and total cross-section measurements on 94,95,96 Mo at n_TOF and GELINA
In: Mattoon CM, Vogt R, Escher J, Thompson I, eds. 15th international conference on nuclear data for science and technology (ND2022). Vol. 284. EPJ web conferences. Les Ulis Cedex A: EDP Sciences; 2023:01031 (4 pp.). https://doi.org/10.1051/epjconf/202328401031
DORA PSI
Nikitin K, Arnold B, Clifford I, Ferroukhi H
Application of CTF subchannel code for BWR reload licensing analysis support
In: 20th international topical meeting on nuclear reactor thermal hydraulics (NURETH-20). Illinois: American Nuclear Society; 2023:5569-5578. https://doi.org/10.13182/NURETH20-40978
DORA PSI
Oprea A, Gunsing F, Schillebeeckx P, Aberle O, Bacak M, Berthoumieux E, et al.
Measurement of the ²⁴¹Am(n,γ) cross section at the n_TOF facility at CERN
In: Mattoon CM, Vogt R, Escher J, Thompson I, eds. 15th international conference on nuclear data for science and technology (ND2022). Vol. 284. EPJ web conferences. Les Ulis Cedex A: EDP Sciences; 2023:01036 (4 pp.). https://doi.org/10.1051/epjconf/202328401036
DORA PSI
Paladino D, Kapulla R, Chae MS, Paranjape S, Mignot G, Kudinov P
PANDA experiment addressing the thermal effects in a large water pool caused by steam and a lighter non-condensable gas release from a multi-hole sparger
In: 20th international topical meeting on nuclear reactor thermal hydraulics (NURETH-20). Illinois: American Nuclear Society; 2023:4006-4019. https://doi.org/10.13182/NURETH20-40388
DORA PSI
Pavón-Rodríguez JA, Alcayne V, Amaducci S, Bacak M, Casanovas A, Cortés-Giraldo MA, et al.
Characterisation of the n_TOF 20 m beam line at CERN with the new spallation target
In: Mattoon CM, Vogt R, Escher J, Thompson I, eds. 15th international conference on nuclear data for science and technology (ND2022). Vol. 284. EPJ web conferences. Les Ulis Cedex A: EDP Sciences; 2023:06006 (6 pp.). https://doi.org/10.1051/epjconf/202328406006
DORA PSI
Petrov V, Ding Y
Passive temperature-sensitive flow-controlling device based on bimetallic membrane deflection, FEM, and CFD feasibility study
In: 20th international topical meeting on nuclear reactor thermal hydraulics (NURETH-20). Illinois: American Nuclear Society; 2023:3690-3700. https://doi.org/10.13182/NURETH20-40808
DORA PSI
Pirovano V, Manna D, Colonna J, Console Camprini E, Cosentino T, Dietz E, et al.
Detector set up for the measurements of the neutron-induced fission cross section of ²³⁵U relative to n-p scattering up to 150 MeV at CERN-n_TOF
In: Mattoon CM, Vogt R, Escher J, Thompson I, eds. 15th international conference on nuclear data for science and technology (ND2022). Vol. 284. EPJ web conferences. Les Ulis Cedex A: EDP Sciences; 2023:01043 (5 pp.). https://doi.org/10.1051/epjconf/202328404019
DORA PSI
Puustinen M, Patel G, Kral P, Nikl T, Clifford I, Trewin R, et al.
LTO modifications to reduce the pts issue - results of TH calculations in the context of the APAL European project
In: Proceedings 20th international topical meeting on nuclear reactor thermal hydraulics (NURETH-20). Illinois: American Nuclear Society; 2023:282-295. https://doi.org/10.13182/NURETH20-40206
DORA PSI
Ramos Perez A, Lind T, Manera A, Petrov V, Prasser H-M
Measurement of aerosol mass transfer and hydrodynamics in a bubble column using Wire-Mesh sensors
In: 20th international topical meeting on nuclear reactor thermal hydraulics (NURETH-20). Illinois: American Nuclear Society; 2023:2402-2415. https://doi.org/10.13182/NURETH20-40223
DORA PSI
Rivera Y, Matteo G, Petrov V, Manera A
Three-dimensional multiphase CFD simulation of a thin liquid film flowing down an inclined plate
In: 20th international topical meeting on nuclear reactor thermal hydraulics (NURETH-20). Illinois: American Nuclear Society; 2023:874-885. https://doi.org/10.13182/NURETH20-40779
DORA PSI
Rochman DA, Koning A, Goriely S
Covariances from model variation: application to quantities for astrophysics
In: Chiba G, Iwamoto O, eds. 5th international workshop on nuclear data covariances (CW2022). Vol. 281. EPJ web conferences. Les Ulis Cedex A: EDP Sciences; 2023:00005 (6 pp.). https://doi.org/10.1051/epjconf/202328100005
DORA PSI
Stamati ME, Torres-Sánchez P, Pérez-Maroto P, Cecchetto M, Goula M, Mastromarco M, et al.
The n_TOF NEAR Station Commissioning and first physics case
In: Mattoon CM, Vogt R, Escher J, Thompson I, eds. 15th international conference on nuclear data for science and technology (ND2022). Vol. 284. EPJ web conferences. Les Ulis Cedex A: EDP Sciences; 2023:06009 (7 pp.). https://doi.org/10.1051/epjconf/202328406009
DORA PSI
Trewin R, Prošek A, Kral P, Clifford I, Perret G, Hartung J, et al.
Evaluation of uncertainties in thermal-hydraulic analyses of PTS for the APAL European project
In: Proceedings of the 20th international topical meeting on nuclear reactor thermal hydraulics. Downers Grove: American Nuclear Society; 2023:5791-5805. https://doi.org/10.13182/NURETH20-40288
DORA PSI
Valori V, Qin S, Petrov V, Manera A
High-fidelity experiments of turbulent buoyant jets from simultaneous particle image velocimetry and laser induced fluorescence
In: 20th international topical meeting on nuclear reactor thermal hydraulics (NURETH-20). Illinois: American Nuclear Society; 2023:2430-2443. https://doi.org/10.13182/NURETH20-41310
DORA PSI
Vocke M, Kapulla R, Morton C, Martinuzzi R
Augmenting PIV temporal resolution via semi-Lagrangian estimation of velocity fluctuations
In: Örlü R, Talamelli A, Peinke J, Oberlack M, eds. Progress in turbulence X. Proceedings of the iTi conference on turbulence 2023. Vol. 404. Springer proceedings in physics; 1066. Cham: Springer; 2023:(6 pp.).
DORA PSI
Welker Z, Manera A, Petrov V, Balestra P
The effects of depressurizing into a cavity for small and medium sized break air ingress accident scenarios
In: 20th international topical meeting on nuclear reactor thermal hydraulics (NURETH-20). Illinois: American Nuclear Society; 2023:3440-3453. https://doi.org/10.13182/NURETH20-40616
DORA PSI
Welker Z, Manera A, Petrov V, Balestra P
The refractive index matched pebble bed facility for high resolution experiments of DLOFC and PLOFC accidents in MPBRs
In: 20th international topical meeting on nuclear reactor thermal hydraulics (NURETH-20). ; 2023:3252-3260. https://doi.org/10.13182/NURETH20-40614
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2022

Ahn T, Huang P-H, Diaz J, Manera A, Petrov V
Experimental study on start-up characteristics of a sodium-filled heat pipe, using in-house high-resolution and high-speed radiation-based imaging system
In: 19th international topical meeting on nuclear reactor thermal hydraulics (NURETH-19). Illinois: American Nuclear Society; 2022:35742 (15 pp.).
DORA PSI
Al-Yahia OS, Clifford I, Nikitin K, Ferroukhi H
Parametric study on the modeling of the open passive containment cooling system (CWC)
Presented at: The 13th international topical meeting on nuclear reactor thermal hydraulics, operation and safety (NUTHOS-13); September 5-10, 2022; Hsinchu.
DORA PSI
Babiano-Suarez V, Balibrea-Correa J, Caballero-Ontanaya L, Domingo-Pardo C, Ladarescu I, Lerendegui-Marco J, et al.
First ⁸⁰Se(n,γ) cross section measurement with high resolution in the full stellar energy range 1 eV - 100 keV and its astrophysical implications for the s-process
In: Liu W, Wang Y, Guo B, Tang X, Zeng S, eds. Symposium on nuclei in the cosmos. 16th symposium on nuclei in the cosmos, NIC-XVI 2021. Les Ulis Cedex A: EDP Sciences; 2022:11026 (8 pp.). https://doi.org/10.1051/epjconf/202226011026
DORA PSI
Che S, Mao J, Sun X, Manera A, Petrov V
Design of high-resolution experiments for extended LOFC accidents HTGRS
In: 19th international topical meeting on nuclear reactor thermal hydraulics (NURETH-19). Illinois: American Nuclear Society; 2022:35301 (16 pp.).
DORA PSI
D'Ambrosi V, Sercombe J, Beajoui S, Chaieb A, Baurens B, Largenton R, et al.
P2M simulation exercise on past fuel melting irradiation experiments: main outcomes on fuel melting assessment in PWR fuel
In: TopFuel 2022 light water reactor fuel performance conference. Illinois: American Nuclear Society; 2022:344-353. https://doi.org/10.13182/TopFuel22-38827
DORA PSI
Diaz J, Serrano-Aguilera JJ, Petrov V, Manera A
Dynamic bias error arising from two-phase flow measurements performed with radiation transmission
In: 19th international topical meeting on nuclear reactor thermal hydraulics (NURETH-19). Illinois: American Nuclear Society; 2022:37372 (16 pp.).
DORA PSI
Diaz J, Liu Q, Petrov V, Manera A, Sun X
High-resolution X-ray radiography methods developed for post-chf experiment
In: 19th international topical meeting on nuclear reactor thermal hydraulics (NURETH-19). Illinois: American Nuclear Society; 2022:35375 (16 pp.).
DORA PSI
Diaz J, Ahn T, Adams R, Petrov V, Manera A
High-resolution tomographic measurements of adiabatic rod bundle
In: 19th international topical meeting on nuclear reactor thermal hydraulics (NURETH-19). Illinois: American Nuclear Society; 2022:35374 (17 pp.).
DORA PSI
Diomidis N, Pudollek S, Wittel M, Frankl M, Vasiliev A
Post-closure canister degradation scenarios in deep geological disposal: preliminary definition and evaluation of potential impact on reactivity
In: Nuclear Criticality Safety division topical meeting (NCSD 2022). La Grange Park: American Nuclear Society; 2022:(7 pp.). https://www.ans.org/pubs/proceedings/article-51979/.
DORA PSI
Doll U, Röhle I, Dues M
Unsteady multi-parameter flow diagnostics by filtered Rayleigh scattering: system design by multi-objective optimisation
In: Proceedings of the 20th international symposium on the application of laser and imaging techniques to fluid mechanics. ; 2022:(18 pp.).
DORA PSI
Espegren F, Suckow D, Lind T, Mantzaras J, Theile J, Ishikawa Y, et al.
Effectiveness of hydrogen recombination by AgX and AgR zeolites
In: Gabrielli F, Herranz LE, Paci S, eds. Proceedings of the 10th European review meeting on severe accidents research (ERMSAR2022). Severe accident research eleven years after the Fukushima accident. sine loco: Karlsruher Institut für Technologie (KIT); 2022:330 (14 pp.).
DORA PSI
Fogliatto E, Clifford I, Ferroukhi H, Puragliesi R
The influence of scaling on turbulent mixing in reactor pressure vessels and core-inlet flow distribution
In: 19th international topical meeting on nuclear reactor thermal hydraulics (NURETH-19). Illinois: American Nuclear Society; 2022:35578 (14 pp.).
DORA PSI
Gupta S, Herranz LE, Lebel LS, Sonnenkalb M, Pellegrini M, Marchetto C, et al.
Integration of pool scrubbing research to enhance source-term calculations (IPRESCA) project
In: 19th international topical meeting on nuclear reactor thermal hydraulics (NURETH-19). Illinois: American Nuclear Society; 2022:33970 (16 pp.).
DORA PSI
Hursin M, Mala P, Vasiliev A, Ferroukhi H, Liu Y, Choi S, et al.
Comparison of CASMO-5, MPACT and Serpent 2 for the modeling of advanced BWR lattices
In: International conference on physics of reactors 2022 (PHYSOR 2022). La Grange Park: American Nuclear Society; 2022:2762-2772.
DORA PSI
Hursin M, Mala P, Vasiliev A, Ferroukhi H, Liu Y, Choi S, et al.
Comparison of CASMO-5, MPACT and Serpent 2 for the modeling of advanced BWR lattices
In: International conference on physics of reactors. Proceedings of the international conference on physics of reactors, PHYSOR 2022. Downers Grove: American Nuclear Society; 2022:2762-2772. https://doi.org/10.13182/PHYSOR22-37760
DORA PSI
Hursin M, Cabelloas O, Palmiotti G
Status of the WPEC subgroup 46 efficient and effective use of integral experiments for nuclear data validation
In: International conference on physics of reactors 2022 (PHYSOR 2022). La Grange Park: American Nuclear Society; 2022:1095-1104. https://doi.org/10.13182/PHYSOR22-37758
DORA PSI
Huxford A, Petrov V, Manera A, Grunloh T
A spectral shift closure model for use in proper orthogonal decomposition-based reduced order models
In: 19th international topical meeting on nuclear reactor thermal hydraulics (NURETH-19). Illinois: American Nuclear Society; 2022:35387 (9 pp.).
DORA PSI
Huxford A, Coppo Leite V, Merzari E, Zou L, Petrov V, Manera A
Development of innovative overlapping-domain coupling between SAM and NekRS
In: 19th international topical meeting on nuclear reactor thermal hydraulics (NURETH-19). Illinois: American Nuclear Society; 2022:35819 (15 pp.).
DORA PSI
Lee H, Vasiliev A, Ferroukhi H
Verification of legacy methodology of minimum critical mass estimation at PSI
Presented at: GLOBAL 2022 - sustainable energy beyond the pandemic; July 6-8, 2022; Reims.
DORA PSI
Lind T, Herranz LE, Sonnenkalb M, Maruyama Y
In-depth analysis for uncertain phenomena on fission product transport in the OECD/NEA ARC-F project
In: 19th international topical meeting on nuclear reactor thermal hydraulics (NURETH-19). Illinois: American Nuclear Society; 2022:34900 (15 pp.).
DORA PSI
Lind T, Kalilainen J, Nichenko S
MSR simulation with cGEMS: salt and fission product evaporation
In: Gabrielli F, Herranz LE, Paci S, eds. Proceedings of the 10th European review meeting on severe accidents research (ERMSAR2022). Severe accident research eleven years after the Fukushima accident. Karlsruhe: Karlsruher Institut für Technologie (KIT); 2022:272 (12 pp.).
DORA PSI
Liu X, Kelm S, Kampili M, Allelein H-J, Kapulla R, Paladino D, et al.
Validation of a finite volume Monte Carlo solver for nongray gas radiation in containment flows
In: 19th international topical meeting on nuclear reactor thermal hydraulics (NURETH-19). Illinois: American Nuclear Society; 2022:19001 (16 pp.).
DORA PSI
Mager T, Hursin M, Fiorina C, Pautz A
Development of a high fidelity model of the CROCUS experimental reactor
In: International conference on physics of reactors 2022 (PHYSOR 2022). La Grange Park: American Nuclear Society; 2022:946-956. https://doi.org/10.13182/PHYSOR22-37250
DORA PSI
Malicki M, Lind T, Kalilainen J
The parametric sensitivity analysis of FPT-1 MELCOR 2.2 input deck as a preparation for uncertainty quantification study
In: Gabrielli F, Herranz LE, Paci S, eds. Proceedings of the 10th European review meeting on severe accidents research (ERMSAR2022). Severe accident research eleven years after the Fukushima accident. Karlsruhe: Karlsruher Institut für Technologie (KIT); 2022:274 (14 pp.).
DORA PSI
Mantzaras J, Theile J, Suckow D, Lind T, Espegren F, Ishikawa Y, et al.
Experimental investigation of hydrogen removal WITH Ag-zeolites under severe accident conditions
In: 19th international topical meeting on nuclear reactor thermal hydraulics (NURETH-19). Illinois: American Nuclear Society; 2022:35581 (14 pp.).
DORA PSI
Mao J, Petrov V, Manera A, Howard T, Cetiner SM
On the development of a novel acoustic flow meter for high-temperature gas-cooled reactors
In: 19th international topical meeting on nuclear reactor thermal hydraulics (NURETH-19). Illinois: American Nuclear Society; 2022:35300 (14 pp.).
DORA PSI
Mao J, Welker Z, Nunez D, Petrov V, Manera A
Validation of rans-based turbulence models against high-resolutional experimental data for buoyancy-driven flow with stratified fronts
In: 19th international topical meeting on nuclear reactor thermal hydraulics (NURETH-19). Illinois: American Nuclear Society; 2022:35611 (16 pp.).
DORA PSI
Martin J-F, Ivanova T, Bess J, Carmouze C, Gan S, Wilson AR, et al.
The OECD NEA Working Party on Nuclear Criticality Safety. Recent outcome, work in progress and outlook
In: Nuclear Criticality Safety division topical meeting (NCSD 2022). La Grange Park: American Nuclear Society; 2022:(10 pp.). https://www.ans.org/pubs/proceedings/article-51992/.
DORA PSI
Mascari F, Bersano A, Massone M, Agnello G, Coindreau O, Beck S, et al.
First outcomes from the phebus FPT1 uncertainty application done in the EU-MUSA project
In: 19th international topical meeting on nuclear reactor thermal hydraulics (NURETH-19). Illinois: American Nuclear Society; 2022:35666 (16 pp.).
DORA PSI
Miniero L, Pandey K, Shcherbanev S, Doll U, Noiray N
Effects of the atomization air on the topology of a Jet A-1 spray flame in a turbulent vitiated crossflow
In: 10th European combustion meeting proceedings. Naples: mcm; 2022:1270-1275.
DORA PSI
Miniero L, Pandey K, Shcherbanev S, Noiray N, Doll U
Tomographic reconstruction of OH density maps for Jet-A1 spray flame in a vitiated crossflow
In: AIAA scitech forum 2022. Reston, VA: American Institute of Aeronautics and Astronautics; 2022:AIAA 2022-1873 (8 pp.). https://doi.org/10.2514/6.2022-1873
DORA PSI
Nikitin K, Arnold B, Clifford I, Ferroukhi H
CPR estimation by CTF subchannel code with machine learning support
Presented at: The 13th international topical meeting on nuclear reactor thermal hydraulics, operation and safety (NUTHOS-13); September5-10, 2022; Hsinchu.
DORA PSI
Papadionysiou M, Seongchan K, Hursin M, Vasiliev A, Ferroukhi H, Pautz A, et al.
Coupling of COBRA-TF to nTRACER for full core high fidelity analysis of VVERs
In: International conference on physics of reactors 2022 (PHYSOR 2022). La Grange Park: American Nuclear Society; 2022:586-595.
DORA PSI
Papadionysiou M, Seongchan K, Hursin M, Vasiliev A, Ferroukhi H, Pautz A, et al.
Coupling of nTRACER to COBRA-TF for full core high-fidelity analysis of VVERs
In: International conference on physics of reactors. Proceedings of the international conference on physics of reactors, PHYSOR 2022. Downers Grove: American Nuclear Society; 2022:586-595. https://doi.org/10.13182/PHYSOR22-37390
DORA PSI
Papadopoulos P, Prasser H-M, Lind T
Gas-liquid mass transfer in bubbly two-phase flows using wire-mesh sensors
In: 19th international topical meeting on nuclear reactor thermal hydraulics (NURETH-19). Illinois: American Nuclear Society; 2022:19001 (16 pp.).
DORA PSI
Park S, Lind T, Birchley J, Steinbrueck M
Current understanding of high-temperature oxidation phenomena during air ingress scenarios
In: Gabrielli F, Herranz LE, Paci S, eds. Proceedings of the 10th European review meeting on severe accidents research (ERMSAR2022). Severe accident research eleven years after the Fukushima accident. Karlsruhe: Karlsruher Institut für Technologie (KIT); 2022:284 (10 pp.).
DORA PSI
Perret G, Clifford I, Ferroukhi H
Bias and uncertainty considerations for trace predictions of RBHT reflood experiments
In: 19th international topical meeting on nuclear reactor thermal hydraulics (NURETH-19). Illinois: American Nuclear Society; 2022:19001 (14 pp.).
DORA PSI
Raffuzzi V, Sublet J-C, Jouanne C, Koning A, Rochman D
An iron evaluation story: from TALYS model parameters to validation on the ASPIS benchmark with the Monte Carlo code TRIPOLI-4®
In: International conference on physics of reactors 2022 (PHYSOR 2022). La Grange Park: American Nuclear Society; 2022:1361-1370.
DORA PSI
Raffuzzi V, Sublet JC, Jouanne C, Koning A, Rochman D
An iron evaluation story: from TALYS model parameters to validation on the ASPIS benchmark with the Monte Carlo code TRIPOLI-4®
In: International conference on physics of reactors. Proceedings of the international conference on physics of reactors, PHYSOR 2022. Downers Grove: American Nuclear Society; 2022:1361-1370. https://doi.org/10.13182/PHYSOR22-37310
DORA PSI
Roth B, Suckow D, Dehbi A
Experimental study of pool scrubbing related bubble hydrodynamics in the globule flow regime
In: 19th international topical meeting on nuclear reactor thermal hydraulics (NURETH-19). Illinois: American Nuclear Society; 2022:35574 (15 pp.).
DORA PSI
Scolaro A, Fiorina C, Siefman D, Hursin M, Pautz A
Bayesian data assimilation for fuel performance based on OFFBEAT
In: International conference on physics of reactors 2022 (PHYSOR 2022). La Grange Park: American Nuclear Society; 2022:3656-3665. https://doi.org/10.13182/PHYSOR22-37357
DORA PSI
Scolaro A, Fiorina C, Clifford I, Brunetto E, Pautz A
Pre-release validation database for the multi-dimensional fuel performance code OFFBEAT
In: International conference on physics of reactors. Proceedings of the international conference on physics of reactors, PHYSOR 2022. Downers Grove: American Nuclear Society; 2022:2914-2923. https://doi.org/10.13182/PHYSOR22-37789
DORA PSI
Shcherbanev S, Morinière T, Solana-Pérez R, Doll U, Noiray N
Flame anchoring of a premixed jet flame in vitiated crossflow using nanosecond repetitively pulsed discharge
In: 10th European combustion meeting proceedings. Naples: mcm; 2022:1425-1429. https://www.ecm2021napoli.eu/proceedings/.
DORA PSI
Sublet JC, Koning A, Rochman D, Gilbert MR, Kahler AC, Jouanne C, et al.
Multifaceted coded nuclear data libraries assemblage, verification and validation: TENDL-2021
In: International conference on radiation shielding and topical meeting of the radiation protection and shielding division. Proceedings of the 14th international conference on radiation shielding and 21st topical meeting of the radiation protection and shielding division, ICRS 2022/RPSD 2022. American Nuclear Society; 2022:308-311. https://doi.org/10.13182/ICRSRPSD22-39025
DORA PSI
Vitullo F, Lamirand V, Ligonnet T, Pakari O, Godat D, Frajtag P, et al.
Millimetric fuel rod displacements: an experimental study of the impact on local thermal neutron flux in the CROCUS reactor
In: International conference on physics of reactors. Proceedings of the international conference on physics of reactors, PHYSOR 2022. Downers Grove: American Nuclear Society; 2022:2632-2641. https://doi.org/10.13182/PHYSOR22-37846
DORA PSI
Vázquez-Rodríguez C, Jiménez G, Andreani M, Paladino D, Paranjape S, Kapulla R, et al.
Simulation of PANDA PE1 spray test using GOTHIC 8.3(QA)
In: 19th international topical meeting on nuclear reactor thermal hydraulics (NURETH-19). Illinois: American Nuclear Society; 2022:35515 (16 pp.).
DORA PSI
Welker Z, Balestra P, Manera A, Petrov V
Oxygen ingress measurements of a scales HTGR facility for small and medium break size DLOFC and air ingress accident scenarios
In: 19th international topical meeting on nuclear reactor thermal hydraulics (NURETH-19). Illinois: American Nuclear Society; 2022:35717 (12 pp.).
DORA PSI
Welker Z, Balestra P, Manera A, Petrov V
PIV measurements of a depressurizing jet to study helium-air mixing during HTGR depressurization accidents

In: 19th international topical meeting on nuclear reactor thermal hydraulics (NURETH-19). Illinois: American Nuclear Society; 2022:35718 (15 pp.).
DORA PSI
Yeo D, Petrov V, Manera A
Application of machine learning for online discovery of component degradation dynamics
In: 19th international topical meeting on nuclear reactor thermal hydraulics (NURETH-19). Illinois: American Nuclear Society; 2022:35385 (16 pp).
DORA PSI
Yeo D, Petrov V, Manera A
Development of the methodology for degradation emulation of primary salt pump in high-temperature fluoride salt test facility
In: Transactions of the American nuclear society. ANS winter meeting and technology expo 2022. Vol. 127. Transactions of the American Nuclear Society. American Nuclear Society; 2022:268-271. https://doi.org/10.13182/T127-39667
DORA PSI
Zahur A, Park J, Cherezov A, Jo Y, Lee D
Reactivity initiated accident uncertainty quantification for fuel assembly with subchannel code
In: International conference on physics of reactors. Proceedings of the international conference on physics of reactors, PHYSOR 2022. Downers Grove: American Nuclear Society; 2022:1667-1676. https://doi.org/10.13182/PHYSOR22-37528
DORA PSI

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2021

Bernal A, Pecchia M, Rochman D, Vasiliev A, Ferroukhi H
Methodology for high-fidelity deterministic modelling of Swiss LWR fuel assemblies
In: Margulis M, Blaise P, eds. PHYSOR2020 - international conference on physics of reactors: transition to a scalable nuclear future. Vol. 247. EPJ web of conferences. Les Ulis Cedex A: EDP Sciences; 2021:06011 (8 pp.). https://doi.org/10.1051/epjconf/202124706011
DORA PSI
Brunetto E, Vitullo F, Lamirand V, Ambrožič K, Godat D, Buck M, et al.
High resolution measurements with miniature neutron scintillators in the SUR-100 zero power reactor
In: Lyoussi A, Carette M, Hodák R, Jenčič I, Le Dû P, Pospíšil S, et al., eds. ANIMMA 2021 - advancements in nuclear instrumentation measurement methods and their applications. Vol. 253. EPJ web of conferences. Les Ulis Cedex A: EDP Sciences; 2021:04029 (8 pp.). https://doi.org/10.1051/epjconf/202125304029
DORA PSI
Cozzo C, Allagbe C, Alonso JR, Ben Ouaghrem K, Cizelj L, Degueldre D, et al.
EUROSAFE: fostering the sharing of nuclear expertise
In: Vázquez-Rodriguez C, Jiménez Carrascosa A, Estevez Albuja S, Duran Vinuesa LF, eds. Book of Proceedings. European nuclear young generation forum 2021. sine loco: European Nuclear Young Generation Forum; 2021:623-626.
DORA PSI
Cozzo C, Lind T, Bertsch J, Nichenko S, Girardin G
Quantifying the benefits of the reduced oxidation kinetics in chromium-coated cladding: a parametric study
In: Vázquez-Rodriguez C, Jiménez Carrascosa A, Estevez Albuja S, Duran Vinuesa LF, eds. Book of Proceedings. European nuclear young generation forum 2021. sine loco: European Nuclear Young Generation Forum; 2021:245-248.
DORA PSI
Fiorina C, Shriwise P, Dufresne A, Ragusa J, Ivanov K, Valentine T, et al.
An initiative for the development and application of open-source multi-physics simulation in support of R&D and E&T in Nuclear Science and Technology
In: Margulis M, Blaise P, eds. PHYSOR2020 - international conference on physics of reactors: transition to a scalable nuclear future. Vol. 247. EPJ web of conferences. Les Ulis Cedex A: EDP Sciences; 2021:02040 (7 pp.). https://doi.org/10.1051/epjconf/202124702040
DORA PSI
Hursin M, Rochman D, Vasiliev A, Ferroukhi H, Pautz A
Impact of various source of covariance information on integral parameters uncertainty during depletion calculations with CASMO-5
In: Margulis M, Blaise P, eds. PHYSOR2020 - international conference on physics of reactors: transition to a scalable nuclear future. Vol. 247. EPJ web of conferences. Les Ulis Cedex A: EDP Sciences; 2021:09005 (10 pp.). https://doi.org/10.1051/epjconf/202124709005
DORA PSI
Hursin M, Vasiliev A, Rochman D, Dokhane A, Ferroukhi H
Monte Carlo analysis of sub-pin resolved power behaviour in modern BWR assembly designs
In: Proceedings of the international conference on mathematics and computational methods applied to nuclear science and engineering (M&C 2021). Illinois: American Nuclear Society (ANS); 2021:758-767. https://doi.org/10.13182/M&C21-33772
DORA PSI
Hursin M, Pakari O, Perret G, Frajtag P, Lamirand V, Pázsit I, et al.
Validation of axial void profile measured by neutron noise techniques in crocus
In: Margulis M, Blaise P, eds. PHYSOR2020 - international conference on physics of reactors: transition to a scalable nuclear future. Vol. 247. EPJ web of conferences. Les Ulis Cedex A: EDP Sciences; 2021:08004 (8 pp.). https://doi.org/10.1051/epjconf/202124708004
DORA PSI
Konarski P, Cozzo C, Khostov G, Ferroukhi H
Extension of Falcon's modelling capabilities to dry storage: development of a new model for hydrogen behavior in duplex claddings
In: TopFuel2021. Brussels: European Nuclear Society; 2021:(10 pp.).
DORA PSI
Lamirand V, Rais A, Pakari O, Hursin M, Laureau A, Pohlus J, et al.
Analysis of the first COLIBRI fuel rods oscillation campaign in the CROCUS reactor for the European project CORTEX
In: Margulis M, Blaise P, eds. PHYSOR2020 - international conference on physics of reactors: transition to a scalable nuclear future. Vol. 247. EPJ web of conferences. Les Ulis Cedex A: EDP Sciences; 2021:21010 (9 pp.). https://doi.org/10.1051/epjconf/202124721010
DORA PSI
Lamirand V, Pakari O, Vitullo F, Ambrožič K, Godat D, Frajtag P, et al.
Local and high distance neutron and gamma measurements of fuel rods oscillation experiments
In: Lyoussi A, Carette M, Hodák R, Jenčič I, Le Dû P, Pospíšil S, et al., eds. ANIMMA 2021 - advancements in nuclear instrumentation measurement methods and their applications. Vol. 253. EPJ web of conferences. Les Ulis Cedex A: EDP Sciences; 2021:04024 (6 pp.). https://doi.org/10.1051/epjconf/202125304024
DORA PSI
Laureau A, Lamirand V, Gruel A, Frajtag P, Pautz A
Dosimetry modeling and experimental validation for the petale program in the CROCUS reactor
In: Margulis M, Blaise P, eds. PHYSOR2020 - international conference on physics of reactors: transition to a scalable nuclear future. Vol. 247. EPJ web of conferences. Les Ulis Cedex A: EDP Sciences; 2021:08015 (10 pp.). https://doi.org/10.1051/epjconf/202124708015
DORA PSI
Mager T, Fiorina C, Hursin M, Pautz A
Validation of the gen-foam model of the crocus experimental reactor
In: Proceedings of the international conference on mathematics and computational methods applied to nuclear science and engineering (M&C 2021). Illinois: American Nuclear Society (ANS); 2021:738-747. https://doi.org/10.13182/M&C21-33754
DORA PSI
Mala P, Pautz A, Ferroukhi H, Vasiliev A
Development of 3D pin-by-pin core solver tortin and coupling with thermal-hydraulics
In: Margulis M, Blaise P, eds. PHYSOR2020 - international conference on physics of reactors: transition to a scalable nuclear future. Vol. 247. EPJ web of conferences. Les Ulis Cedex A: EDP Sciences; 2021:02034 (8 pp.). https://doi.org/10.1051/epjconf/202124702034
DORA PSI
Mylonakis AG, Demazière C, Vinai P, Lamirand V, Rais A, Pakari O, et al.
Core SIM+ simulations of COLIBRI fuel rods oscillation experiments and comparison with measurements
In: Margulis M, Blaise P, eds. PHYSOR2020 - international conference on physics of reactors: transition to a scalable nuclear future. Vol. 247. EPJ web of conferences. Les Ulis Cedex A: EDP Sciences; 2021:21006 (9 pp.). https://doi.org/10.1051/epjconf/202124721006
DORA PSI
Pakari O, Lamirand V, Mager T, Laureau A, Frajtag P, Pautz A
First in-core gamma spectroscopy experiments in a zero power reactor
In: Lyoussi A, Carette M, Hodák R, Jenčič I, Le Dû P, Pospíšil S, et al., eds. ANIMMA 2021 - advancements in nuclear instrumentation measurement methods and their applications. Vol. 253. EPJ web of conferences. Les Ulis Cedex A: EDP Sciences; 2021:04022 (8 pp.). https://doi.org/10.1051/epjconf/202125304022
DORA PSI
Pakari O, Mancusi D, Petit O, Zoia A, Lamirand V, Pautz A
Towards the validation of noise experiments in the CROCUS reactor using the TRIPOLI-4 Monte Carlo code in analog mode
In: Margulis M, Blaise P, eds. PHYSOR2020 - international conference on physics of reactors: transition to a scalable nuclear future. Vol. 247. EPJ web of conferences. Les Ulis Cedex A: EDP Sciences; 2021:04007 (9 pp.). https://doi.org/10.1051/epjconf/202124704007
DORA PSI
Papadionysiou M, Seongchan K, Hursin M, Vasiliev A, Ferroukhi H, Pautz A, et al.
Coupling of nTRACER to COBRA-TF for high-fidelity analysis of VVERs
In: Margulis M, Blaise P, eds. PHYSOR2020 - international conference on physics of reactors: transition to a scalable nuclear future. Vol. 247. EPJ web of conferences. Les Ulis Cedex A: EDP Sciences; 2021:02008 (8 pp.). https://doi.org/10.1051/epjconf/202124702008
DORA PSI
Papadionysiou M, Kim S, Hursin M, Vasiliev A, Ferroukhi H, Joo HG, et al.
Validation of the high-resolution code nTRACER against VVER-1000 hot zero power measurements
In: Proceedings of the international conference on mathematics and computational methods applied to nuclear science and engineering (M&C 2021). Illinois: American Nuclear Society (ANS); 2021:700-709. https://doi.org/10.13182/M&C21-33678
DORA PSI
Perret G, Rochman D, Vasiliev A, Ferroukhi H
Neutron emission measurements of PWR spent fuel segments and preliminary validation of depletion calculations
In: Margulis M, Blaise P, eds. PHYSOR2020 - international conference on physics of reactors: transition to a scalable nuclear future. Vol. 247. EPJ web of conferences. Les Ulis Cedex A: EDP Sciences; 2021:10004 (10 pp.). https://doi.org/10.1051/epjconf/202124710004
DORA PSI
Pázsit I, Hursin M, Nylén H, Dykin V
Reconstructing the axial void velocity profile in BWRS from measurements of the in-core neutron noise
In: Margulis M, Blaise P, eds. PHYSOR2020 - international conference on physics of reactors: transition to a scalable nuclear future. Vol. 247. EPJ web of conferences. Les Ulis Cedex A: EDP Sciences; 2021:02013 (8 pp.). https://doi.org/10.1051/epjconf/202124702013
DORA PSI
Scolaro A, Fiorina C, Van Uffelen P, Schubert A, Clifford I, Pautz A
Coupling methodology between TRANSURANUS and the multi-dimensional fuel performance code OFFBEAT
In: Proceedings 2021 ANS winter meeting. Vol. 125. Transactions of the American Nuclear Society. American Nuclear Society; 2021:520-523. https://doi.org/10.13182/T125-36688
DORA PSI
Szabolcs Ványi A, Hursin M, Czifrus S
Investigation of recently introduced diffusion coefficient generation methods
In: Cizelj L, Tekavčič M, eds. NENE2021 conference proceedings. Ljubljana: Nuclear Society of Slovenia; 2021:311 (8 pp.).
DORA PSI
Tasakos T, Ioannou G, Verma V, Alexandridis G, Dokhane A, Stafylopatis A
Deep learning-based anomaly detection in nuclear reactor cores
In: Tasakos T, Ioannou G, Verma V, Alexandridis G, Dokhane A, Stafylopatis A, eds. Proceedings of the international conference on mathematics and computational methods applied to nuclear science and engineering (M&C 2021). Illinois: American Nuclear Society (ANS); 2021:2026-2037. https://doi.org/10.13182/M&C21-33681
DORA PSI
Torres LA, Chionis D, Montalvo C, Dokhane A, García-Berrocal A
Neutron noise spectral features of simulated mechanical and thermal-hydraulic perturbations in a PWR core
In: Margulis M, Blaise P, eds. PHYSOR2020 - international conference on physics of reactors: transition to a scalable nuclear future. Vol. 247. EPJ web of conferences. Les Ulis Cedex A: EDP Sciences; 2021:21001 (8 pp.). https://doi.org/10.1051/epjconf/202124721001
DORA PSI
Valentine T, Avramova M, Fleming M, Hursin M, Ivanov K, Petruzzi A, et al.
Overview of the OECD-NEA expert group on multi-physics experimental data, benchmarks and validation
In: Margulis M, Blaise P, eds. PHYSOR2020 - international conference on physics of reactors: transition to a scalable nuclear future. Vol. 247. EPJ web of conferences. Les Ulis Cedex A: EDP Sciences; 2021:06048 (8 pp.). https://doi.org/10.1051/epjconf/202124706048
DORA PSI
Vasiliev A, Pecchia M, Rochman D, Ferroukhi H
Enhancement of validation studies for reactor dosimetry and activation predictions with the nuclear data sampling methodology
In: Margulis M, Blaise P, eds. PHYSOR2020 - international conference on physics of reactors: transition to a scalable nuclear future. Vol. 247. EPJ web of conferences. Les Ulis Cedex A: EDP Sciences; 2021:10021 (8 pp.). https://doi.org/10.1051/epjconf/202124710021
DORA PSI
Verma V, Chionis D, Dokhane A, Ferroukhi H
Modelling and analysis of fuel assembly vibrational modes in PWRs using SIMULATE-3K
In: Margulis M, Blaise P, eds. PHYSOR2020 - international conference on physics of reactors: transition to a scalable nuclear future. Vol. 247. EPJ web of conferences. Les Ulis Cedex A: EDP Sciences; 2021:21008 (8 pp.). https://doi.org/10.1051/epjconf/202124721008
DORA PSI
Vitullo F, Lamirand V, Ambrožič K, Braun L, Godat D, Frajtag P, et al.
Design of a 150-miniature detectors 3D core-mapping system for the CROCUS reactor
In: Lyoussi A, Carette M, Hodák R, Jenčič I, Le Dû P, Pospíšil S, et al., eds. ANIMMA 2021 - advancements in nuclear instrumentation measurement methods and their applications. Vol. 253. EPJ web of conferences. Les Ulis Cedex A: EDP Sciences; 2021:04023 (8 pp.). https://doi.org/10.1051/epjconf/202125304023
DORA PSI

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2020

Alcayne V, Mendoza E, Cano-Ott D, Kimura A, Aberle O, Amaducci S, et al.
Measurement of the ²⁴⁴Cm capture cross sections at both CERN n_TOF experimental areas
In: Ge Z, Shu N, Chen Y, Wang W, Zhang H, eds. ND 2019: international conference on nuclear data for science and technology. Vol. 239. EPJ web of conferences. Sine loco: EDP Sciences; 2020:01034 (5 pp.). https://doi.org/10.1051/epjconf/202023901034
DORA PSI
Alhassan E, Rochman D, Vasiliev A, Bergmann RM, Wohlmuther M, Koning AJ, et al.
In search of the best nuclear data file for proton induced reactions: varying both models and their parameters
In: Ge Z, Shu N, Chen Y, Wang W, Zhang H, eds. ND 2019: international conference on nuclear data for science and technology. Vol. 239. EPJ web of conferences. Sine loco: EDP Sciences; 2020:13005 (4 pp.). https://doi.org/10.1051/epjconf/202023913005
DORA PSI
Ambrožič K, Lamirand V, Hübner S, Hursin M, Rais A, Pakari O, et al.
Noise analysis techniques of in-core modulation experiments for the European project CORTEX
In: Snoj L, Čufar A, eds. NENE 2020 conference proceedings. Ljubljana: Nuclear Society of Slovenia; 2020:212 (8 pp.).
DORA PSI
Babiano-Suarez V, Aberle O, Alcayne V, Amaducci S, Andrzejewski J, Audouin L, et al.
⁸⁰Se(n,γ) cross-section measurement at CERN n_TOF
In: Nuclear physics in astrophysics IX (NPA-IX). Vol. 1668. Journal of physics: conference series. Bristol, UK: IOP Publishing; 2020:012001 (8 pp.). https://doi.org/10.1088/1742-6596/1668/1/012001
DORA PSI
Casanovas A, Tarifeño-Saldivia AE, Domingo-Pardo C, Calviño F, Maugeri E, Guerrero C, et al.
Neutron capture measurement at the n_TOF facility of the ²⁰⁴Tl and ²⁰⁵Tl s-process branching points
In: Nuclear physics in astrophysics IX (NPA-IX). Vol. 1668. Journal of physics: conference series. Bristol, UK: IOP Publishing; 2020:012005 (9 pp.). https://doi.org/10.1088/1742-6596/1668/1/012005
DORA PSI
Chiaveri E, Aberle O, Alcayne V, Amaducci S, Andrzejewski J, Audouin L, et al.
Status and perspectives of the neutron time-of-flight facility n_TOF at CERN
In: Ge Z, Shu N, Chen Y, Wang W, Zhang H, eds. ND 2019: international conference on nuclear data for science and technology. Vol. 239. EPJ web of conferences. Les Ulis Cedex A: EDP Sciences; 2020:17001 (8 pp.). https://doi.org/10.1051/epjconf/202023917001
DORA PSI
Clifford I, Zerkak O, Ferroukhi H
Making the switch from pipe to vessel components
In: Advances in thermal hydraulics (ATH'20). La Grange Park: American Nuclear Society; 2020:157-170.
DORA PSI
Domingo-Pardo C, Babiano-Suarez V, Balibrea-Correa J, Caballero L, Ladarescu I, Lerendegui-Marco J, et al.
Review and new concepts for neutron-capture measurements of astrophysical interest
In: Nuclear physics in astrophysics IX (NPA-IX). Vol. 1668. Journal of physics: conference series. Bristol, UK: IOP Publishing; 2020:012013 (13 pp.). https://doi.org/10.1088/1742-6596/1668/1/012013
DORA PSI
Eleme Z, Patronis N, Stamatopoulos A, Tsinganis A, Kokkoris M, Michalopoulou V, et al.
First results of the ²⁴¹Am(n,f) cross section measurement at the experimental area 2 of the n_TOF facility at CERN
In: Ge Z, Shu N, Chen Y, Wang W, Zhang H, eds. ND 2019: international conference on nuclear data for science and technology. Vol. 239. EPJ web of conferences. Sine loco: EDP Sciences; 2020:05014 (5 pp.). https://doi.org/10.1051/epjconf/202023905014
DORA PSI
Fischer U, Avrigeanu M, Avrigeanu V, Konobeyev A, Kodeli I, Leeb H, et al.
Nuclear data activities of the EUROfusion consortium
In: Ge Z, Shu N, Chen Y, Wang W, Zhang H, eds. ND 2019: international conference on nuclear data for science and technology. Vol. 239. EPJ web of conferences. Les Ulis Cedex A: EDP Sciences; 2020:21001 (7 pp.). https://doi.org/10.1051/epjconf/202023921001
DORA PSI
Jiang Y, Laureau A, Lamirand V, Frajtag P, Pautz A
In-core dosimetry for the validation of neutron spectra in the CROCUS reactor
In: Lyoussi A, Giot M, Carette M, Jenčič I, Reynard-Carette C, Vermeeren L, et al., eds. ANIMMA 2019 - advancements in nuclear instrumentation measurement methods and their applications. Vol. 225. EPJ web of conferences. Les Ulis Cedex A: EDP Sciences; 2020:04021 (6 pp.). https://doi.org/10.1051/epjconf/202022504021
DORA PSI
Lamirand V, Rais A, Hübner S, Lange C, Pohlus J, Paquee U, et al.
Neutron noise experiments in the AKR-2 and CROCUS reactors for the European project CORTEX
In: Lyoussi A, Giot M, Carette M, Jenčič I, Reynard-Carette C, Vermeeren L, et al., eds. ANIMMA 2019 - advancements in nuclear instrumentation measurement methods and their applications. Vol. 225. EPJ web of conferences. Les Ulis Cedex A: EDP Sciences; 2020:04023 (6 pp.). https://doi.org/10.1051/epjconf/202022504023
DORA PSI
Lamirand V, Laureau A, Pakari O, Frajtag P, Pautz A
Power calibration methodology at the CROCUS reactor
In: Lyoussi A, Giot M, Carette M, Jenčič I, Reynard-Carette C, Vermeeren L, et al., eds. ANIMMA 2019 - advancements in nuclear instrumentation measurement methods and their applications. Vol. 225. EPJ web of conferences. Les Ulis Cedex A: EDP Sciences; 2020:04022 (5 pp.). https://doi.org/10.1051/epjconf/202022504022
DORA PSI
Lamirand V, Frajtag P, Godat D, Pakari O, Laureau A, Rais A, et al.
The COLIBRI experimental program in the CROCUS reactor: characterization of the fuel rods oscillator
In: Lyoussi A, Giot M, Carette M, Jenčič I, Reynard-Carette C, Vermeeren L, et al., eds. ANIMMA 2019 - advancements in nuclear instrumentation measurement methods and their applications. Vol. 225. EPJ web of conferences. Les Ulis Cedex A: EDP Sciences; 2020:04020 (5 pp.). https://doi.org/10.1051/epjconf/202022504020
DORA PSI
Laureau A, Lamirand V, Rochman D, Pautz A
Bayesian Monte Carlo assimilation for the PETALE experimental programme using inter-dosimeter correlation
In: Ge Z, Shu N, Chen Y, Wang W, Zhang H, eds. ND 2019: international conference on nuclear data for science and technology. Vol. 239. EPJ web of conferences. Les Ulis Cedex A: EDP Sciences; 2020:18004 (4 pp.). https://doi.org/10.1051/epjconf/202023918004
DORA PSI
Manna A, Aberle O, Alcayne V, Amaducci S, Andrzejewski J, Audouin L, et al.
Setup for the measurement of the ²³⁵U(n,f) cross section relative to n-p scattering up to 1 GeV
In: Ge Z, Shu N, Chen Y, Wang W, Zhang H, eds. ND 2019: international conference on nuclear data for science and technology. Vol. 239. EPJ web of conferences. Sine loco: EDP Sciences; 2020:01008 (5 pp.). https://doi.org/10.1051/epjconf/202023901008
DORA PSI
Mastromarco M. M, Mazzone A, Massimi C, Cristallo S, Colonna N, Aberle O, et al.
The ¹⁵⁴Gd neutron capture cross section measured at the n_TOF facility and its astrophysical implications

In: Ge Z, Shu N, Chen Y, Wang W, Zhang H, eds. ND 2019: international conference on nuclear data for science and technology. Vol. 239. EPJ web of conferences. Sine loco: EDP Sciences; 2020:07003 (5 pp.). https://doi.org/10.1051/epjconf/202023907003
DORA PSI
Mendoza E, Alcayne V, Cano-Ott D, Kimura A, Skarbeli AV, Aberle O, et al.
Study of photon strength functions of ²⁴¹Pu and ²⁴⁵Cm from neutron capture measurements
In: Ge Z, Shu N, Chen Y, Wang W, Zhang H, eds. ND 2019: international conference on nuclear data for science and technology. Vol. 239. EPJ web of conferences. Les Ulis Cedex A: EDP Sciences; 2020:05006 (6 pp.). https://doi.org/10.1051/epjconf/202023901015
DORA PSI
Mengoni A, Damone LA, Barbagallo M, Aberle O, Alcayne V, Amaducci S, et al.
New reaction rates for the destruction of ⁷Be during big bang nucleosynthesis measured at CERN/n_TOF and their implications on the cosmological lithium problem
In: Ge Z, Shu N, Chen Y, Wang W, Zhang H, eds. ND 2019: international conference on nuclear data for science and technology. Vol. 239. EPJ web of conferences. Sine loco: EDP Sciences; 2020:07001 (4 pp.). https://doi.org/10.1051/epjconf/202023907001
DORA PSI
Michalopoulou V, Stamatopoulos A, Vlastou R, Kokkoris M, Tsinganis A, Diakaki M, et al.
First results of the ²³⁰Th(n,f) cross section measurements at the CERN n_TOF facility
In: Ge Z, Shu N, Chen Y, Wang W, Zhang H, eds. ND 2019: international conference on nuclear data for science and technology. Vol. 239. EPJ web of conferences. Sine loco: EDP Sciences; 2020:05004 (6 pp.). https://doi.org/10.1051/epjconf/202023905004
DORA PSI
Mora DF, Niffenegger M, Mukin R
Crack propagation modeling in a PWR under PTS Using XFEM
In: Materials and fabrication. Vol. 6. Pressure vessels and piping conference. New York, NY, USA: ASME; 2020:V006T06A001. https://doi.org/10.1115/PVP2020-21026
DORA PSI
Oprea A, Gunsing F, Schillebeeckx P, Aberle O, Bacak M, Berthoumieux E, et al.
Neutron capture cross section measurements of ²⁴¹Am at the n_TOF facility
In: Ge Z, Shu N, Chen Y, Wang W, Zhang H, eds. ND 2019: international conference on nuclear data for science and technology. Vol. 239. EPJ web of conferences. Les Ulis Cedex A: EDP Sciences; 2020:01009 (5 pp.). https://doi.org/10.1051/epjconf/202023901009
DORA PSI
Pakari O, Lamirand V, Vandereydt B, Vitullo F, Hursin M, Kong C, et al.
Design and simulation of gamma spectrometry experiments in the CROCUS reactor
In: Lyoussi A, Giot M, Carette M, Jenčič I, Reynard-Carette C, Vermeeren L, et al., eds. ANIMMA 2019 - advancements in nuclear instrumentation measurement methods and their applications. Vol. 225. EPJ web of conferences. Les Ulis Cedex A: EDP Sciences; 2020:04016 (6 pp.). https://doi.org/10.1051/epjconf/202022504016
DORA PSI
Sublet JC, Koning A, Rochman D, Gilbert MR, Kahler AC, Jouanne C, et al.
Multitaceted coded nuclear data libraries assemblage, verification and validation: TENDL-2019
In: Fabian J, Michal R, Corradini ML, Martin W, Klein AC, Bibao y Leon S, et al., eds. 2020 transactions of the American Nuclear Society Winter Meeting, ANS 2020. Vol. 123. Transactions of the American Nuclear Society. Illinois: American Nuclear Society; 2020:1227-1230. https://doi.org/10.13182/T123-33321
DORA PSI
Terranova N, Aberle O, Alcayne V, Amaducci S, Andrzejewski J, Audouin L, et al.
Monte Carlo simulations and n-p differential scattering data measured with Proton Recoil Telescopes
In: Ge Z, Shu N, Chen Y, Wang W, Zhang H, eds. ND 2019: international conference on nuclear data for science and technology. Vol. 239. EPJ web of conferences. Les Ulis Cedex A: EDP Sciences; 2020:01024 (5 pp.). https://doi.org/10.1051/epjconf/202023901024
DORA PSI
Vasiliev A, Pecchia M, Rochman D, Perret G, Ferroukhi H, Laureau A, et al.
Assessment of representativity of the PETALE experiments for validation of Swiss LWRs ex-core dosimetry calculations
In: Ge Z, Shu N, Chen Y, Wang W, Zhang H, eds. ND 2019: international conference on nuclear data for science and technology. Vol. 239. EPJ web of conferences. Les Ulis Cedex A: EDP Sciences; 2020:22001 (6 pp.). https://doi.org/10.1051/epjconf/202023922001
DORA PSI
Vasiliev A, Pecchia M, Rochman D, Ferroukhi H, Alhassan E
On the impact of nuclear data uncertainties on LWR neutron dosimetry assessments
In: Ge Z, Shu N, Chen Y, Wang W, Zhang H, eds. ND 2019: international conference on nuclear data for science and technology. Vol. 239. EPJ web of conferences. Les Ulis Cedex A: EDP Sciences; 2020:22003 (4 pp.). https://doi.org/10.1051/epjconf/202023922003
DORA PSI
Vitullo F, Lamirand V, Mosset J-B, Frajtag P, Pakari O, Perret G, et al.
Developing and testing a miniature fiber-coupled scintillator for in-core neutron counting in CROCUS
In: Lyoussi A, Giot M, Carette M, Jenčič I, Reynard-Carette C, Vermeeren L, et al., eds. ANIMMA 2019 - advancements in nuclear instrumentation measurement methods and their applications. Vol. 225. EPJ web of conferences. Les Ulis Cedex A: EDP Sciences; 2020:04018 (8 pp.). https://doi.org/10.1051/epjconf/202022504018
DORA PSI

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2019

Alcayne V, Kimura A, Mendoza E, Cano-Ott D, Aberle O, Amaducci S, et al.
Measurement of the ²⁴⁴Cm and ²⁴⁶Cm neutron-induced cross sections at the n_TOF facility
In: García-Ramos J-E, Andrés MV, Pérez-Bernal F, Valera JA, Moro AM, eds. Basic concepts in nuclear physics: theory, experiments and applications. 2018 La Rábida international scientific meeting on nuclear physics. Vol. 225. Springer proceedings in physics. Cham: Springer; 2019:117-122. https://doi.org/10.1007/978-3-030-22204-8_4
DORA PSI
Alcayne V, Kimura A, Mendoza E, Cano-Ott D, Martínez T, Aberle O, et al.
Measurement of the ²⁴⁴Cm and ²⁴⁶Cm neutron-induced capture cross sections at the n_TOF facility
In: Serot O, Chebboubi A, eds. WONDER-2018 - 5th international workshop on nuclear data evaluation for reactor applications. Vol. 211. EPJ web of conferences. sine loco: EDP Sciences; 2019:03008 (8 pp.). https://doi.org/10.1051/epjconf/201921103008
DORA PSI
Andreani M, Paranjape S
Modelling of the interaction of two heat sources simulating the thermal effects of PARs
Presented at: ICAPP 2019 - International congress on advances in nuclear power plants; May 12-15, 2019; Juan-les-pins, France.
DORA PSI
Babiano-Suarez V, Caballero L, Domingo-Pardo C, Ladarescu I, Aberle O, Alcayne V, et al.
Characterization and first test of an i-TED prototype at CERN n_TOF
In: García-Ramos J-E, Andrés MV, Pérez-Bernal F, Valera JA, Moro AM, eds. Basic concepts in nuclear physics: theory, experiments and applications. 2018 La Rábida international scientific meeting on nuclear physics. Vol. 225. Springer proceedings in physics. Cham: Springer; 2019:169-173. https://doi.org/10.1007/978-3-030-22204-8_18
DORA PSI
Barbagallo M, Aberle O, Alcayne V, Andrzejewski J, Audouin L, Bécares V, et al.
(n,cp) reactions study at the n_TOF facility at CERN: results for the cosmological lithium problem
In: Cerutti F, Ferrari A, Kawano T, Salvat-Pujol F, Talou P, eds. Proceedings of the 15th international conference on nuclear reaction mechanisms. Geneva: CERN; 2019:259-264.
DORA PSI
Chionis D, Dokhane A, Ferroukhi H, Pautz A
Spatial localization of perturbation propagation in LWRs using causality and connectivity analysis
In: International conference on mathematics and computational methods applied to nuclear science and engineering (M&C 2019). La Grange Park, USA: American Nuclear Society (ANS); 2019:1960-1969.
DORA PSI
Clifford I, Cozzo C, Ferroukhi H
First assessments of the dynamic gap conductance model in TRACE
In: 18th international topical meeting on nuclear reactor thermal hydraulics (NURETH-18). La Grange Park, USA: American Nuclear Society (ANS); 2019:4624-4636.
DORA PSI
Cozzo C, Ngayam-Happy R, Chen J-C, Pecchia M, Girardin G
Modeling of the U₃Si₂/SiC fuel system behavior for a RIA scenario
In: Global/top fuel 2019. LaGrange Park, IL, USA: American Nuclear Society (ANS); 2019:643-647.
DORA PSI
Dokhane A, Hursin M, Vasiliev A, Ferroukhi H, Grandi G
Impact of implicit effects on uncertainties in SPERT-III Rod Ejection Accident experiments
In: International conference on mathematics and computational methods applied to nuclear science and engineering (M&C 2019). La Grange Park: American Nuclear Society; 2019:2765-2774.
DORA PSI
Falsetti C, Kapulla R, Paranjape S, Paladino D
Thermal radiation effect on thermocouple measurements
In: SWINTH-2019. Specialists workshop on advanced instrumentation and measurement techniques for experiments related to nuclear reactor thermal hydraulics and severe accidents. sine loco: sine nomine; 2019:054 (11 pp.).
DORA PSI
Fernandez Moguel L, Lind T, Rýdl A
Analysis of fission product transport in unit 3 of Fukushima Daiichi
In: 18th international topical meeting on nuclear reactor thermal hydraulics (NURETH-18). La Grange Park: American Nuclear Society (ANS); 2019:508-521.
DORA PSI
Gallego-Marcos I, Villanueva W, Kapulla R, Paranjape S, Paladino D, Kudinov P
Modeling of thermal stratification and mixing induced by steam injection through spargers into a large water pool
In: Computational fluid dynamics for nuclear reactor safety applications-6 (CFD4NRS-6). Workshop proceedings. sine loco: OECD; NEA; 2019:(17 pp.).
DORA PSI
Herranz LE, Pellegrini M, Lind T, Sonnenkalb M, Godin-Jacqmin L, López C, et al.
Overview and outcomes of the OECD/NEA benchmark study of the accident at the Fukushima Daiichi NPS (BSAF) phase II – results of severe accident analyses for Unit 1
In: 18th international topical meeting on nuclear reactor thermal hydraulics (NURETH-18). La Grange Park: American Nuclear Society (ANS); 2019:1107-1118.
DORA PSI
Hursin M, Pakari O, Perret G, Frajtag P, Lamirand V, Pázsit I, et al.
Measurement of the gas velocity in a water-air mixture in crocus by neutron noise technique
In: International conference on mathematics computational methods applied to nuclear science and engineering (M&C 2019). La Grange Park: American Nuclear Society (ANS); 2019:(8 pp.).
DORA PSI
Hursin M, Park J, Kim W, Siefman D, Perret G, Vasiliev A, et al.
Uncertainty quantification of LWR-proteus phase II experiments using CASMO-5
In: International conference on mathematics computational methods applied to nuclear science and engineering (M&C 2019). La Grange Park: American Nuclear Society (ANS); 2019:(9 pp.).
DORA PSI
Jäckel BS, Lind T, Fernandez-Moguel L, Steinbrück M, Park S
Application of a newly developed computer code model for nitriding and re-oxidation of cladding materials on separate effect tests and integral experiments
In: Proceedings of the ERMSAR 2019. sine loco: sine nomine; 2019:024 (14 pp.).
DORA PSI
Kalilainen J, Lind T, Stuckert J, Stegmaier U
Aerosol results of the QUENCH-18 bundle test
In: Proceedings of the ERMSAR 2019. sine loco: sine nomine; 2019:019 (11 pp.).
DORA PSI
Kapulla R, Paranjape S, Falsetti C, Paladino D
High spatial resolution PIV measurements in the PANDA facility
Presented at: ICAPP 2019 - international congress on advances in nuclear power plants; May 12-15, 2019; Juan-les-pins, France.
DORA PSI
Lamirand V, Laureau A, Rochman D, Perret G, Gruel A, Leconte P, et al.
An experimental programme optimized with uncertainty propagation: PETALE in the CROCUS reactor
In: Serot O, Chebboubi A, eds. WONDER-2018 - 5th international workshop on nuclear data evaluation for reactor applications. Vol. 211. EPJ web of conferences. sine loco: EDP Sciences; 2019:03003 (5 pp.). https://doi.org/10.1051/epjconf/201921103003
DORA PSI
Laureau A, Lamirand V, Rochman D, Pautz A
Total Monte Carlo acceleration for the PETALE experimental programme in the CROCUS reactor
In: Serot O, Chebboubi A, eds. WONDER-2018 - 5th international workshop on nuclear data evaluation for reactor applications. Vol. 211. EPJ web of conferences. sine loco: EDP Sciences; 2019:03002 (5 pp.). https://doi.org/10.1051/epjconf/201921103002
DORA PSI
Lind T, Campbell S, Herranz LE, Kissane M, Song JH
A summary of fission-product-transport phenomena during SGTR severe accidents
In: 18th international topical meeting on nuclear reactor thermal hydraulics (NURETH-18). La Grange Park, IL, USA: American Nuclear Society (ANS); 2019:4063-4075.
DORA PSI
Lind T, Pellegrini M, Herranz LE, Sonnenkalb M, Nishi Y, Tamaki H, et al.
Overwiew and outcomes of the OECD/NEA benchmark study of the accident at the Fukushima Daiichi NPS (BSAF) phase II – results of severe accident analyses for Unit 3
In: 18th international topical meeting on nuclear reactor thermal hydraulics (NURETH-18). La Grange Park: American Nuclear Society (ANS); 2019:1133-1146.
DORA PSI
Mala P, Pautz A, Ferroukhi H
EPR fuel cycle depletion with pin-by-pin code tortin and nodal code SIMULATE5
In: International conference on mathematics and computational methods applied to nuclear science and engineering (M&C 2019). La Grange Park, USA: American Nuclear Society (ANS); 2019:1640-1649.
DORA PSI
Manara D, Jacquemain D, Van Dorsselaere JP, Bottomley PD, Adorni M, Journeau C, et al.
Severe accident research priority ranking: a new assessment eight years after the Fukushima Daiichi accident
In: Proceedings of the ERMSAR 2019. sine loco: sine nomine; 2019:1-25.
DORA PSI
Massimi C, Aberle O, Alcayne V, Andrzejewski J, Audouin l., Bécares V, et al.
Data for the s process from n_TOF
In: Formicola A, Junker M, Gialanella L, Imbriani G, eds. Nuclei in the cosmos XV. Vol. 219. Springer proceedings in physics. Cham: Springer; 2019:63-70. https://doi.org/10.1007/978-3-030-13876-9_11
DORA PSI
Mora DF, Mukin R, Costa Garrido O, Niffenegger M
Fracture mechanics analysis of a PWR under PTS using XFEM and input from TRACE
In: Materials and fabrication: advanced and additive manufacturing and material technologies. Vol. 6A. PVP - American Society of Mechanical Engineers. Pressure vessels and piping division. sine loco: American Society of Mechanical Engineers (ASME); 2019:PVP2019-94019 (7 pp.). https://doi.org/10.1115/PVP2019-94019
DORA PSI
Mukin R, Clifford I, Costa Garrido O, Mora DF, Niffenegger M, Niceno B, et al.
Screening analysis for pressurized thermal shock (PTS) transient scenarios
In: 18th international topical meeting on nuclear reactor thermal hydraulics (NURETH-18). La Grange Park, USA: American Nuclear Society (ANS); 2019:2536-2549.
DORA PSI
Niffenegger M, Garrido OC, Mora DF, Qian G, Mukin R, Sharabi M, et al.
Uncertainties in pressurized thermal shock analyses
In: Design and analysis: 4th international symposium on coke drum life cycle management. Vol. 3. PVP - American society of mechanical engineers. Pressure vessels and piping division. sine loco: American Society of Mechanical Engineers (ASME); 2019:PVP2019-94076 (10 pp.). https://doi.org/10.1115/PVP2019-94076
DORA PSI
Nikitin K, Clifford I, Ferroukhi H
PMSYS: plant management system as a part of Swiss Simulation Platform
In: 18th international topical meeting on nuclear reactor thermal hydraulics (NURETH-18). LaGrange Park, USA: American Nuclear Society (ANS); 2019:2943-2954.
DORA PSI
Papadionysiou M, Seongchan K, Hursin M, Vasiliev A, Ferroukhi H, Pautz A, et al.
Assessment of nTRACER and parcs performance for VVER configurations
In: International conference on mathematics and computational methods applied to nuclear science and engineering (M&C 2019). La Grange Park, USA: American Nuclear Society (ANS); 2019:700-709.
DORA PSI
Papadopoulos P, Tietze S, Suckow D, Ceder SJ, Roth B, Lind T
Hydrodynamic characterisation inside a wet scrubber for different flow regimes relevant for pool scrubbing and FCVS
In: Proceedings of the ERMSAR 2019. Prague: AF POWER agency; 2019:028 (10 pp.).
DORA PSI
Paranjape S, Kapulla R, Mignot G, Paladino D
Gas redistribution caused by interacting sources in the presence of a vertical condenser
Presented at: ICAPP 2019 - international congress on advances in nuclear power plants; May 12-15, 2019; Juan-les-pins, France.
DORA PSI
Pellegrini M, Herranz L, Sonnenkalb M, Lind T, Maruyana Y, Gaunt R, et al.
Main findings, remaining uncertainties and lessons learned from the OECD/NEA BSAF project
In: 18th international topical meeting on nuclear reactor thermal hydraulics (NURETH-18). La Grange Park: American Nuclear Society (ANS); 2019:1147-1162.
DORA PSI
Puragliesi R, Mukin R, Clifford I, Ferroukhi H, Seidl M
Comparison of computational fluid dynamics and subchannel numerical solutions of fuel assemblies characterized by bowing
In: 18th international topical meeting on nuclear reactor thermal hydraulics (NURETH-18). La Grange Park: American Nuclear Society (ANS); 2019:2209-2222.
DORA PSI
Rais A, Lamirand V, Pakari O, Laureau A, Pohlus J, Pohl C, et al.
Towards the validation of neutron noise simulators: qualification of data acquisition systems
In: International conference on mathematics and computational methods applied to nuclear science and engineering (M&C 2019). Illinois: American Nuclear Society (ANS); 2019:2638-2647.
DORA PSI
Scolaro A, Clifford I, Fiorina C, Pautz A
Cladding plasticity modeling with the multidimensional fuel performance code OFFBEAT
In: Global/top fuel 2019. LaGrange Park, IL, USA: American Nuclear Society (ANS); 2019:47-55.
DORA PSI
Scolaro A, Robert Y, Fiorina C, Clifford I, Pautz A
Coupling methodology for the multidimensional fuel performance code OFFBEAT and the Monte Carlo neutron transport code Serpent
In: Global/top fuel 2019. LaGrange Park, IL, USA: American Nuclear Society (ANS); 2019:1174-1183.
DORA PSI
Siefman D, Hursin M, Pautz A
Data assimilation of post irradiation examination experiments to adjust fission yields
In: Ge Z, Shu N, Chen Y, Wang W, Zhang H, eds. ND 2019: international conference on nuclear data for science and technology. Vol. 239. EPJ web of conferences. Les Ulis Cedex A: EDP Sciences; 2019:13004 (4 pp.). https://doi.org/10.1051/epjconf/202023913004
DORA PSI
Sonnenkalb M, Pellegrini M, Herranz LE, Lind T, Morreale AC, Kanda K, et al.
Overview and outcomes of the OECD/NEA benchmark study of the accident at the Fukushima Daiichi NPS (BSAF) phase II – results of severe accident analyses for unit 2
In: 18th international topical meeting on nuclear reactor thermal hydraulics (NURETH-18). La Grange Park: American Nuclear Society (ANS); 2019:1119-1132.
DORA PSI
Tagliente G, Aberle O, Alcayne V, Andrzejewski J, Audouin L, Babiano-Suarez V, et al.
Nuclear astrophysics at n_TOF facility, CERN
In: Cerutti F, Ferrari A, Kawano T, Salvat-Pujol F, Talou P, eds. Proceedings of the 15th international conference on nuclear reaction mechanisms. Geneva: CERN; 2019:251-258.
DORA PSI
Tassan-Got L, Colonna N, Diakaki M, Eleme Z, Manna A, Sekhar A, et al.
Fission program at n_TOF
In: Serot O, Chebboubi A, eds. WONDER-2018 - 5th international workshop on nuclear data evaluation for reactor applications. Vol. 211. EPJ Web of Conferences. sine loco: EDP Sciences; 2019:03006 (9 pp.). https://doi.org/10.1051/epjconf/201921103006
DORA PSI
Verma V, Demazière C, Vinai P, Ricciardi G, Jacqmin R
Assessment of the neutron noise induced by stationary fuel assembly vibrations in a light water reactor
In: International conference on mathematics and computational methods applied to nuclear science and engineering (M&C 2019). La Grange Park: American Nuclear Society (ANS); 2019:1124-1133.
DORA PSI
Wolfertz A, Adams R, Perret G
First tests of a gamma-blind fast neutron detector prototype based on ZnS and wavelength-shifting fibers
In: Annual meeting 2019. Vol. 120. Transactions of the American Nuclear Society. La Grange Park: American Nuclear Society; 2019:426-428.
DORA PSI

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2018

Andreani M, Kapulla R
Analyses of gas stratification erosion by a vertical jet in presence of an obstacle using the GOTHIC code
In: Proceedings of the 26th international conference on nuclear engineering (ICONE26). Thermal hydraulics and safety analyses. Vol. 6B. New York: American Society of Mechanical Engineers (ASME); 2018:ICONE26-82360 (11 pp.). https://doi.org/10.1115/ICONE26-82360
DORA PSI
Bates E, Zhang D, Truong B, Sui D, Hu W, Su GH, et al.
Conclusions of a benchmark study on the EBR-II SHRT-45R experiment
In: Fast reactors and related fuel cycles: next generation nuclear systems for sustainable development (FR17). Proceedings of an international conference organized by the International Atomic Energy Agency, hosted by the government of the Russian Federation through the state atomic energy corporation "Rosatom" and held in Yekaterinburg, Russian Federation, 26–29 June 2017. Vol. CN245. Proceedings series (International Atomic Energy Agency). Vienna: International Atomic Energy Agency; 2018:372 (10 pp.).
DORA PSI
Batra C, Kriventsev V, Monti S, Briggs L, Hu W, Sui D, et al.
IAEA's coordinated research project on EBR-II shutdown heat removal tests: an overview
In: Fast reactors and related fuel cycles: next generation nuclear systems for sustainable development (FR17). Proceedings of an international conference organized by the International Atomic Energy Agency, hosted by the government of the Russian Federation through the state atomic energy corporation "Rosatom" and held in Yekaterinburg, Russian Federation, 26–29 June 2017. Vol. CN245. Proceedings series (International Atomic Energy Agency). Vienna: International Atomic Energy Agency; 2018:361 (8 pp.).
DORA PSI
Beghi I, Tietze S, Lind T, Prasser H-M
Effect of hydrodynamics on the retention of iodine in a wet scrubber
In: International congress on advances in nuclear power plants (ICAPP 2018). Vol. 1. Illinois: American Nuclear Society; 2018:302-309.
DORA PSI
Briggs L, Kriventsev V, Monti S, Hu W, Sui D, Su G, et al.
Benchmark analyses of EBR-II shutdown heat removal tests
In: Fast reactors and related fuel cycles: next generation nuclear systems for sustainable development (FR17). Proceedings of an international conference organized by the International Atomic Energy Agency, hosted by the government of the Russian Federation through the state atomic energy corporation "Rosatom" and held in Yekaterinburg, Russian Federation, 26–29 June 2017. Vol. CN245. Proceedings series (International Atomic Energy Agency). Vienna: International Atomic Energy Agency; 2018:004 (10 pp.).
DORA PSI
Casanovas A, Domingo-Pardo C, Guerrero C, Lerendegui-Marco J, Calviño F, Tarifeño-Saldivia A, et al.
Measurement of the radiative capture cross section of the s-process branching points ²⁰⁴Tl and ¹⁷¹Tm at the n_TOF facility (CERN)
In: Sun Y, ed. 16th international symposium on capture gamma-ray spectroscopy and related topics (CGS16). Vol. 178. EPJ web of conferences. sine loco: EDP Sciences; 2018:03004 (5 pp.). https://doi.org/10.1051/epjconf/201817803004
DORA PSI
Chionis D, Dokhane A, Ferroukhi H, Girardin G, Pautz A
PWR neutron noise phenomenology: part I - simulation of stochastic phenomena with simulate-3K
In: Proceedings of the PHYSOR 2018. LaGrange Park, IL, USA: American Nuclear Society; 2018:1001-1012.
DORA PSI
Chionis D, Dokhane A, Ferroukhi H, Girardin G, Pautz A
PWR neutron noise phenomenology: part II - qualitative comparison against plant data
In: Proceedings of the PHYSOR 2018. LaGrange Park, IL, USA: American Nuclear Society; 2018:1013-1024.
DORA PSI
Cozzo C, Khvostov G
ATF developments in FALCON V1 at PSI
In: Topfuel 2018. Part 4. Brussels: European Nuclear Society; 2018:A0112 (9 pp.).
DORA PSI
De Sousa Ribeiro F, Calivá F, Chionis D, Dokhane A, Mylonakis A, Demazière C, et al.
Towards a deep unified framework for nuclear reactor perturbation analysis
In: Sundaram S, ed. Proceedings of the 2018 IEEE symposium series on computational intelligence (SSCI 2018). Piscataway: IEEE; 2018:120-127. https://doi.org/10.1109/SSCI.2018.8628637
DORA PSI
Di Filippo M, Krepel J, Mikityuk K, Prasser H-M
Analysis of major group structures used for nuclear reactor simulations
In: Proceedings of the 26th international conference on nuclear engineering (ICONE26). Student paper competition. New York: American Society of Mechanical Engineers (ASME); 2018:ICONE26-81445 (10 pp.). https://doi.org/10.1115/ICONE26-81445
DORA PSI
Dokhane A, Vasiliev A, Rochman D, Ferroukhi H, Grandi G
Analyses of the SPERT-III RIA experiments with nuclear data uncertainty quantification using three different covariance matrix libraries
In: Proceedings of the PHYTRA4 conference. sine loco: American Nuclear Society (ANS); 2018:91-102.
DORA PSI
Dokhane A, Chionis D, Ferroukhi H
Towards systematic and continuous tracking of neutron and process noise signatures during LWR operation
In: International conference on physics of reactors (PHYSOR 2018). Reactor physics paving the way towards more efficient systems. Red Hook: Curran Associates, Inc.; 2018:3005-3016.
DORA PSI
Griffin PJ, Koning A, Rochman D
Importance of treating correlations in the uncertainty quantification of radiation damage metrics
In: Radiation protection and shielding division 20th topical meeting. Illinois: American Nuclear Society (ANS); 2018:(10 pp.).
DORA PSI
Hombourger B, Krepel J, Mikityuk K, Pautz A
On the feasibility of Breed-and-Burn fuel cycles in Molten Salt Reactors
In: Fast reactors and related fuel cycles: next generation nuclear systems for sustainable development (FR17). Proceedings of an international conference organized by the International Atomic Energy Agency, hosted by the government of the Russian Federation through the state atomic energy corporation "Rosatom" and held in Yekaterinburg, Russian Federation, 26–29 June 2017. Vol. CN245. Proceedings series (International Atomic Energy Agency). Vienna: International Atomic Energy Agency; 2018:388 (11 pp.).
DORA PSI
Hursin M, Siefman D, Perret G, Rochman D, Vasiliev A, Ferroukhi H
Determination of sobol sensitivity indices for correlated inputs with SHARK-X
In: Proceedings of the PHYSOR 2018. LaGrange Park, IL, USA: American Nuclear Society; 2018:(12 pp.).
DORA PSI
Hursin M, Siefman D, Perret G, Pautz A
Representativity analysis of the LWR-PROTEUS Phase II experiments using SHARKX stochastic sampling method
In: ANS international conference on best-estimate plus uncertainties methods (BEPU-2018). La Grange Park: American Nuclear Society; 2018:277 (12 pp.).
DORA PSI
Hursin M
The importance of experimental uncertainty in the BEPU Approach
In: ANS international conference on best-estimate plus uncertainties methods (BEPU-2018). La Grange Park: American Nuclear Society; 2018:KNA4 (12 pp.).
DORA PSI
Jung B, Vasiliev A, Pecchia M, Ferroukhi H
Optimization and sensitivity studies towards PWR structures activation characterization using the MCNP code
Presented at: 2018 student conference; April 5-7, 2018; University of Florida, Gainesville, FL, USA.
DORA PSI
Jäckel BS, Lind T, Fernandez-Moguel L, Steinbrück M, Park S
Development of a computer code model for nitriding and re‐oxidation of cladding materials under severe accident conditions
In: Proceedings of the international conference nuclear energy for New Europe (NENE 2018). Ljubljana: Nuclear Society of Slovenia; 2018:506.1 (8 pp.).
DORA PSI
Kalilainen J, Kim H, Dehbi A, Lind T
Aerosol depletion in natural circulation in simplified geometry
In: International congress on advances in nuclear power plants (ICAPP 2018). Vol. 1. Illinois: American Nuclear Society; 2018:571-577.
DORA PSI
Kalilainen J, Lind T, Prasser H-M
Loss of forced cooling accident analysis of HTR-PM using MELCOR 2.2 code
In: Proceedings of HTR 2018. sine loco: sine nomine; 2018:(7 pp.).
DORA PSI
Krepel J
Comparison of fast reactors performance in the closed U-Pu and Th-U cycle
In: Fast reactors and related fuel cycles: next generation nuclear systems for sustainable development (FR17). Proceedings of an international conference organized by the International Atomic Energy Agency, hosted by the government of the Russian Federation through the state atomic energy corporation "Rosatom" and held in Yekaterinburg, Russian Federation, 26–29 June 2017. Vol. CN245. Proceedings series (International Atomic Energy Agency). Vienna: International Atomic Energy Agency; 2018:052 (10 pp.).
DORA PSI
Kromer H, Adams R, Soubelet B, Zboray R, Prasser HM
Improvement of a compact fast neutron generator for imaging applications
In: 2018 IEEE nuclear science symposium and medical imaging conference proceedings (NSS/MIC). sine loco: IEEE; 2018:(3 pp.). https://doi.org/10.1109/NSSMIC.2018.8824470
DORA PSI
Lamirand V, Perret G, Radman S, Siefman D, Frajtag P, Hursin M, et al.
Design of separated element reflector experiments in CROCUS: PETALE
In: Sparks MH, DePriest KR, Vehar DW, eds. Reactor dosimetry: 16th international symposium. West Conshohocken, USA: ASTM International; 2018:1-14. https://doi.org/10.1520/STP160820170090
DORA PSI
Lamirand V, De Izzarra G, Krasa A, Perret G, Pakari O, Frajtag P, et al.
Intercomparison of neutron noise measurement systems in the CROCUS reactor
In: Proceedings of the PHYSOR 2018. LaGrange Park, IL, USA: American Nuclear Society; 2018:(11 pp.).
DORA PSI
Mambelli S, Mikityuk K, Panadero A-L
Chugging boiling in low-void SFR core: new phenomenology of unprotected loss of flow
In: Fast reactors and related fuel cycles: next generation nuclear systems for sustainable development (FR17). Proceedings of an international conference organized by the International Atomic Energy Agency, hosted by the government of the Russian Federation through the state atomic energy corporation "Rosatom" and held in Yekaterinburg, Russian Federation, 26–29 June 2017. Vol. CN245. Proceedings series (International Atomic Energy Agency). Vienna: International Atomic Energy Agency; 2018:451 (9 pp.).
DORA PSI
Mikityuk K, Girardi E, Krepel J, Bubelis E, Fridman E, Rineiski A, et al.
ESFR-SMART: new Horizon-2020 project on SFR safety
In: Fast reactors and related fuel cycles: next generation nuclear systems for sustainable development (FR17). Proceedings of an international conference organized by the International Atomic Energy Agency, hosted by the government of the Russian Federation through the state atomic energy corporation "Rosatom" and held in Yekaterinburg, Russian Federation, 26–29 June 2017. Vol. CN245. Proceedings series (International Atomic Energy Agency). Vienna: International Atomic Energy Agency; 2018:450 (10 pp.).
DORA PSI
Mukin R, Rochman D, Clifford I, Vasiliev A, Ferroukhi H
Effect of nuclear data on the DNBR prediction with subchannel code COBRA-TF
In: ANS international conference on best-estimate plus uncertainties methods (BEPU-2018). La Grange Park: American Nuclear Society; 2018:285 (6 pp.).
DORA PSI
Mukin R, Clifford I, Ferroukhi H, Niffenegger M
Pressurized Thermal Shock (PTS) transient scenarios analysis with TRACE
In: Proceedings of the 26th international conference on nuclear engineering (ICONE26). Thermal hydraulics and safety analyses. New York: American Society of Mechanical Engineers (ASME); 2018:ICONE26-81749 (7 pp.). https://doi.org/10.1115/ICONE26-81749
DORA PSI
Mukin R, Seidl M, Clifford I, Ferroukhi H
Sensitivity of CTF solution to subchannel window size
In: Proceedings of the 26th international conference on nuclear engineering (ICONE26). Thermal hydraulics and safety analyses. New York: American Society of Mechanical Engineers (ASME); 2018:ICONE26-82546 (11 pp.). https://doi.org/10.1115/ICONE26-82546
DORA PSI
Ngayam-Happy R, Cozzo C, Khvostov G, Krack M, Ferroukhi H
Fuel thermo-mechanical simulations with uncertainty quantification and sensitivity analysis of the OECD/NEA RIA code benchmark using FALCON and URANIE
In: ANS international conference on best-estimate plus uncertainties methods (BEPU-2018). La Grange Park: American Nuclear Society; 2018:2018-124 (11 pp.).
DORA PSI
Pakari O, Lamirand V, Perret G, Braun L, Frajtag P, Pautz A
Current mode neutron noise measurements in the zero power reactor CROCUS
In: Lyoussi A, Carette M, Giot M, Le Dû P, Reynard-Carette C, Schyns M, et al., eds. ANIMMA 2017 - advancements in nuclear instrumentation measurement methods and their applications. Vol. 170. EPJ web of conferences. Les Ulis Cedex A: EDP Sciences; 2018:04017 (5 pp.). https://doi.org/10.1051/epjconf/201817004017
DORA PSI
Pakari O, Lamirand V, Perret G, Godat D, Hursin M, Frajtag P, et al.
Investigation of spatial effects on neutron noise measurements in the zero power reactor CROCUS
In: Proceedings of the PHYSOR 2018. LaGrange Park, IL, USA: American Nuclear Society; 2018:(12 pp.).
DORA PSI
Papadopoulos P, Lind T, Prasser H-M
Analyzing droplet size distributions inside a self-priming venturi scrubber for filtered containment venting systems
In: Proceedings of the 2018 26th international conference on nuclear engineering (ICONE26). Thermal hydraulics and safety analyses. New York: American Society of Mechanical Engineers (ASME); 2018:ICONE26-82227 (7 pp.). https://doi.org/10.1115/ICONE26-82227
DORA PSI
Paviet P, Alekseev P, Fazio C, Fratoni M, Hwang I, Kelly J, et al.
GEN IV education and training initiative via public webinars
In: Fast reactors and related fuel cycles: next generation nuclear systems for sustainable development (FR17). Proceedings of an international conference organized by the International Atomic Energy Agency, hosted by the government of the Russian Federation through the state atomic energy corporation "Rosatom" and held in Yekaterinburg, Russian Federation, 26–29 June 2017. Vol. CN245. Vienna: International Atomic Energy Agency; 2018:009 (8 pp.).
DORA PSI
Pecchia M, Ferroukhi H, Vasiliev A, Grimm P
Studies of intra-pin power distributions in operated BWR fuel assemblies using MCNP with a cycle check-up methodology
In: PHYSOR 2018: reactor physics paving the way towards more efficient systems. International Conference on Physics of Reactors, PHYSOR 2018: Reactor Physics Paving the Way Towards More Efficient Systems. Red Hook: Curran Associates, Inc.; 2018:(12 pp.).
DORA PSI
Pelloni S, Panadero A-L, Mikityuk K, Pautz A
Low-void-effect sodium-cooled core: uncertainty of local sodium void reactivity as a result of nuclear data uncertainties
In: Fast reactors and related fuel cycles: next generation nuclear systems for sustainable development (FR17). Proceedings of an international conference organized by the International Atomic Energy Agency, hosted by the government of the Russian Federation through the state atomic energy corporation "Rosatom" and held in Yekaterinburg, Russian Federation, 26–29 June 2017. Vol. CN245. Proceedings series (International Atomic Energy Agency). Vienna: International Atomic Energy Agency; 2018:050 (10 pp.).
DORA PSI
Perret G, Rahman S, Wicaksono D
Deterministic sampling and Gaussian Process metamodel approach applied to a station black out accident model
Presented at: ANS best estimate plus uncertainty international conference (BEPU 2018); May 13-18, 2018; Lucca, Italy.
DORA PSI
Perret G, Wicaksono D
Global sensitivity analysis and registration strategy for temperature profiles of reflood experiment simulations
In: ANS international conference on best-estimate plus uncertainties methods (BEPU-2018). La Grange Park: American Nuclear Society; 2018:098 (14 pp.).
DORA PSI
Prasser H-M, Janasz F, Suckow D, Szogradi M
Non-condensable gas plugging and mixing behavior in PWR steam generator tubes during reflux condensation
In: Proceedings of the 26th international conference on nuclear engineering (ICONE26). Thermal hydraulics and safety analyses. New York: American Society of Mechanical Engineers (ASME); 2018:ICONE26-82350 (10 pp.). https://doi.org/10.1115/ICONE26-82350
DORA PSI
Puragliesi R, Mukin R, Clifford I, Ferroukhi H, Seidl M
Computational fluid dynamics as a tool for deriving subchannel model parameters - The PSBT case study
In: Proceedings of the 26th international conference on nuclear engineering (ICONE26). Computational fluid dynamics (CFD); nuclear education and public acceptance. Vol. 8. New York: American Society of Mechanical Engineers (ASME); 2018:ICONE26-81743 (13 pp.). https://doi.org/10.1115/ICONE26-81743
DORA PSI
Rimpault G, Buiron L, Stauff NE, Kim TK, Taiwo TA, Lee Y-K, et al.
Objectives and status of the OECD/NEA sub-group on Uncertainty Analysis in Modelling (UAM) for Design, Operation and Safety Analysis of SFRs (SFR-UAM)
In: Fast reactors and related fuel cycles: next generation nuclear systems for sustainable development (FR17). Proceedings of an international conference organized by the International Atomic Energy Agency, hosted by the government of the Russian Federation through the state atomic energy corporation "Rosatom" and held in Yekaterinburg, Russian Federation, 26–29 June 2017. Vol. CN245. Proceedings series (International Atomic Energy Agency). Vienna: International Atomic Energy Agency; 2018:220 (13 pp.).
DORA PSI
Rochman D, Vasiliev A, Ferroukhi H, Janin D, Seidl M
Best estimate plus uncertainty analysis for the ²⁴⁴CM prediction in spent fuel characterization
Presented at: ANS best estimate plus uncertainty international conference (BEPU 2018); May 13-18, 2018; Lucca, Italy.
DORA PSI
Scolaro A, Clifford I, Fiorina C, Pautz A
First steps towards the development of a 3D nuclear fuel behaviour solver with OpenFOAM
In: Proceedings of the 26th international conference on nuclear engineering (ICONE26). Nuclear fuel and material, reactor physics, and transport theory. Vol. 3. sine loco: American Society of Mechanical Engineers (ASME); 2018:ICONE26-82381 (10 pp.). https://doi.org/10.1115/ICONE26-82381
DORA PSI
Siefman D, Hursin M, Aufiero M, Bidaud A, Pautz A
Convergence analysis and criterion for data assimilation with sensitivities from Monte Carlo neutron transport codes
In: Proceedings of the PHYSOR 2018. LaGrange Park, IL, USA: American Nuclear Society; 2018:(10 pp.).
DORA PSI
Sublet J-C, Koning A, Rochman D
TENDL-2017: the making of multi-faceted technological nuclear data library
In: Radiation protection and shielding division 20th topical meeting. Illinois: American Nuclear Society (ANS); 2018:(7 pp.).
DORA PSI
Tambouratzis T, Chionis D, Dokhane A
General regression neural networks for the concurrent, timely and reliable identification of detector malfunctions and/or nuclear reactor deviations from steady-state operation
In: Sundaram S, ed. Proceedings of the 2018 IEEE symposium series on computational intelligence (SSCI 2018). Piscataway: IEEE; 2018:524-531. https://doi.org/10.1109/SSCI.2018.8628700
DORA PSI
Vasiliev A, Herrero J, Rochman D, Pecchia M, Ferroukhi H, Caruso S
Criticality safety evaluations for the concept of Swiss PWR spent fuel geological repository
In: ANS international conference on best-estimate plus uncertainties methods (BEPU-2018). La Grange Park: American Nuclear Society; 2018:229 (12 pp.).
DORA PSI
Vasiliev A, Rochman D, Pecchia M, Ferroukhi H
On the importance of the neutron scattering angular distributions for the LWR fast neutron dosimetry
In: International conference on physics of reactors (PHYSOR 2018). Reactor physics paving the way towards more efficient systems. Red Hook: Curran Associates, Inc.; 2018:3686-3697.
DORA PSI
Vitullo F, Krepel J, Kalilainen J, Prasser H-M, Pautz A
Statistical burnup distribution of moving pebbles in HTR-PM reactor
In: Proceedings of the 26th international conference on nuclear engineering (ICONE26). Student Paper Competition. New York: American Society of Mechanical Engineers (ASME); 2018:ICONE26-81082 (10 pp.). https://doi.org/10.1115/ICONE26-81082
DORA PSI

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2017

Albiol T, Herranz L, Riera E, Dalibart C, Lind T, Del Corno A, et al.
The European PASSAM project: R&D outcomes towards enhanced severe accident source term mitigation
In: International congress on advances in nuclear power plants. 2017 international congress on advances in nuclear power plants, ICAPP 2017 - a new paradigm in nuclear power safety, proceedings. sine loco: International congress on advances in nuclear power plants, ICAPP; 2017:(10 pp.).
DORA PSI
Aounallah Y
Post-dryout heat transfer assessment of trace
In: 37th annual conference of the canadian nuclear society and 41st annual cns/cna student conference. Canadian Nuclear Society; 2017.
DORA PSI
Aounallah Y
Simulations with TRACE of a BWR/4 steam line break under "hot standby" conditions
In: 37th annual conference of the canadian nuclear society & 41st CNS/CNA student conference 2017. Vol. 1. Toronto, Ontario, Canada: Canadian Nuclear Society; 2017:218-228.
DORA PSI
Aounallah Y
TRACE/S3K code coupling simulations of a BWR/4 anticipated transient without scram
In: Proceedings of the 37th annual conference of the Canadian Nuclear Society & 41st CNS/CNA student conference 2017. Vol. 2. Toronto: Canadian Nuclear Society (CNS); 2017:1000-1013.
DORA PSI
Cabellos O, Alvarez-Velarde F, Angelone M, Diez CJ, Dyrda J, Fiorito L, et al.
Benchmarking and validation activities within JEFF project
In: Siegler P, Mondelaers W, Plompen A, Hambsch F-J, Schillebeeckx P, Kopecky S, et al., eds. International conference on nuclear data for science and technology. Vol. 146. EPJ Web of Conferences. EDP Sciences; 2017:06004 (6 pp.). https://doi.org/10.1051/epjconf/201714606004
DORA PSI
Chionis D, Dokhane A, Belblidia L, Pecchia M, Giardin G, Ferroukhi H, et al.
SIMULATE-3K analyses of neutron noise response to fuel assembly vibrations and thermal-hydraulics parameters fluctuations
In: Proceedings of the international conference on mathematics & computational methods applied to nuclear science & engineering (M&C 2017). Daejeon: Korean Nuclear Society; 2017:P289 (8 pp.).
DORA PSI
Chollet M, Cozzo C, Bertsch J, Martin M, Grolimund D, Samson V-A
New insights in the fuel grain subdivision during in-plant irradiation up to high burn-up
Presented at: Water reactor fuel performance meeting 2017 (WRFPM 2017); September 10-14, 2017; Jeju, Korea.
DORA PSI
Coindreau O, Jäckel B, Rocchi F, Alcaro F, Angelova D, Bandini G, et al.
Severe accident code-to-code comparison for two accident scenarios in a spent fuel pool
Presented at: 8th European review meeting on severe accident research (ERMSAR 2017); May 16-18, 2017; Warsaw, Poland.
DORA PSI
Cozzo C, Bertsch J, Fave L, Rahman S, Dokhane A, Krack M, et al.
SiC cladding behavior: experiments and modelling at PSI
Presented at: Water reactor fuel performance meeting 2017 (WRFPM 2017); September 10-14, 2017; Jeju, Korea.
DORA PSI
Dehbi A, Kelm S, Kalilainen J, Mueller H
The influence of thermal radiation on the free convection inside enclosures
Presented at: 8th European review meeting on severe accident research (ERMSAR 2017); May 16-18, 2017; Warsaw, Poland.
DORA PSI
Dokhane A, Grandi G, Leray O, Rochman D, Vasiliev A, Ferroukhi H
Nuclear data uncertainty decomposition for SPERT-III RIA experiments using SIMULATE-3K and SHARK-X
In: Proceedings of the international conference on mathematics & computational methods applied to nuclear science & engineering (M&C 2017). Daejeon: Korean Nuclear Society; 2017:P236 (8 pp.).
DORA PSI
Fischer U, Avrigeanu M, Avrigeanu V, Cabellos O, Dzysiuk N, Koning A, et al.
Nuclear data for fusion technology - the European approach
In: Siegler P, Mondelaers W, Plompen A, Hambsch F-J, Schillebeeckx P, Kopecky S, et al., eds. International conference on nuclear data for science and technology. Vol. 146. EPJ Web of Conferences. EDP Sciences; 2017:09003 (6 pp.). https://doi.org/10.1051/epjconf/201714609003
DORA PSI
Fischer U, Angelone M, Avrigeanu M, Avrigeanu V, Bachmann C, Dzysiuk N, et al.
The role of nuclear data for fusion nuclear technology
Presented at: International symposium on fusion nuclear technology; September 25-29, 2017; Kyoto, Japan.
DORA PSI
Fleming M, Sublet J-C, Gilbert MR, Koning A, Rochman D
TALYS/TENDL verification and validation processes: Outcomes and recommendations
In: Plompen A, Hambsch F-J, Schillebeeckx P, Mondelaers W, Heyse J, Kopecky S, et al., eds. ND 2016: international conference on nuclear data for science and technology. Vol. 146. EPJ web of conferences. sine loco: EDP Sciences; 2017:02033 (4 pp.). https://doi.org/10.1051/epjconf/201714602033
DORA PSI
García-Herranz N, Panadero A-L, Martinez A, Pelloni S, Mikityuk K, Pautz A
Nuclear data sensitivity and uncertainty assessment of sodium voiding reactivity coefficients of an ASTRID-like sodium fast reactor
In: Plompen A, Hambsch F-J, Schillebeeckx P, Mondelaers W, Heyse J, Kopecky S, et al., eds. ND 2016: international conference on nuclear data for science and technology. Vol. 146. EPJ web of conferences. sine loco: EDP Sciences; 2017:09006 (6 pp.). https://doi.org/10.1051/epjconf/201714609006
DORA PSI
Griffin P, Rochman D, Koning A
Characterization of the energy-dependent uncertainty and correlation in silicon neutron displacement damage metrics
In: Plompen A, Hambsch F-J, Schillebeeckx P, Mondelaers W, Heyse J, Kopecky S, et al., eds. ND 2016: international conference on nuclear data for science and technology. Vol. 146. EPJ web of conferences. sine loco: EDP Sciences; 2017:02008 (6 pp.). https://doi.org/10.1051/epjconf/201714602008
DORA PSI
Herrero JJ, Rochman D, Leray O, Vasiliev A, Pecchia M, Ferroukhi H, et al.
Impact of nuclear data uncertainty on safety calculations for spent nuclear fuel geological disposal
In: Plompen A, Hambsch F-J, Schillebeeckx P, Mondelaers W, Heyse J, Kopecky S, et al., eds. ND 2016: international conference on nuclear data for science and technology. Vol. 146. EPJ web of conferences. sine loco: EDP Sciences; 2017:09028 (4 pp.). https://doi.org/10.1051/epjconf/201714609028
DORA PSI
Hursin M, Leray O, Perret G, Pautz A, Bostelmann F, Aures A, et al.
Impact of implicit effects on uncertainties and sensitivities of the Doppler coefficient of a LWR pin cell
In: Plompen A, Hambsch F-J, Schillebeeckx P, Mondelaers W, Heyse J, Kopecky S, et al., eds. ND 2016: international conference on nuclear data for science and technology. Vol. 146. EPJ web of conferences. sine loco: EDP Sciences; 2017:09034 (5 pp.). https://doi.org/10.1051/epjconf/201714609034
DORA PSI
Jaeckel B, Steiner P, Klügel J-U
Progression of postulated loss-of-cooling accidents in the wet storage pool of NPP Gösgen/Däniken
In: Proceedings of NENE 2017. Ljubljana: Nuclear Society of Slovenia; 2017:402.1 (8 pp.).
DORA PSI
Leray O, Rochman D, Fleming M, Sublet J-C, Koning A, Vasiliev A, et al.
Fission yield covariances for JEFF: a Bayesian Monte Carlo method
In: Plompen A, Hambsch F-J, Schillebeeckx P, Mondelaers W, Heyse J, Kopecky S, et al., eds. ND 2016: international conference on nuclear data for science and technology. Vol. 146. EPJ web of conferences. sine loco: EDP Sciences; 2017:09023 (4 pp.). https://doi.org/10.1051/epjconf/201714609023
DORA PSI
Mala P, Pautz A, Canepa S, Ferroukhi H
Nodal and pin-by-pin calculations comparison with codes SIMULATE-5 and DYN3D
In: International conference on mathematics & computational methods applied to nuclear science & engineering (M&C 2017). Daejeon: Korean Nuclear Society; 2017:(9 pp.).
DORA PSI
Mukin R, Clifford I, Ferroukhi H, Seidl M
Thermal hydraulic analysis of PWR assembly bowing using subchannel code COBRA-TF
Presented at: 17th international topical meeting on nuclear reactor thermal hydraulics (NURETH 2017); September 3-8, 2017; Xi'an, China.
DORA PSI
Mukin R, Puragliesi R, Ceuca SC, Austregesilo H, Bousbia Salah A
Thermal mixing assessment using 3-D thermal-hydraulic and CFD codes
Presented at: 17th international topical meeting on nuclear reactor thermal hydraulics (NURETH 2017); September 3-8, 2017; Xi'an, China.
DORA PSI
Palmiotti G, Salvatores M, Hursin M, Kodeli I, Gabrielli F, Hummel A
New approaches to provide feedback from nuclear and covariance data adjustment for effective improvement of evaluated nuclear data files
In: Plompen A, Hambsch F-J, Schillebeeckx P, Mondelaers W, Kopecky S, Siegler P, et al., eds. ND 2016: international conference on nuclear data for science and technology. Vol. 146. EPJ web of conferences. sine loco: EDP Sciences; 2017:06003 (11 pp.). https://doi.org/10.1051/epjconf/201714606003
DORA PSI
Pettersen EE, Mikityuk K
Simulating circulating-fuel fast reactors with the coupled TRACE-PARCS code
In: Fast reactors and related fuel cycles: next generation nuclear systems for sustainable development (FR17). Proceedings of an international conference organized by the International Atomic Energy Agency, hosted by the government of the Russian Federation through the state atomic energy corporation "Rosatom" and held in Yekaterinburg, Russian Federation, 26–29 June 2017. Vol. CN245. Proceedings series (International Atomic Energy Agency). Vienna: International Atomic Energy Agency; 2017:059 (10 pp.).
DORA PSI
Rochman D, Mala P, Ferroukhi H, Vasiliev A, Seidl M, Janin D, et al.
Bowing effects on power and burn-up distributions for simplified full PWR and BWR cores
In: Proceedings of the international conference on mathematics & computational methods applied to nuclear science & engineering (M&C 2017). Daejeon: Korean Nuclear Society; 2017:P286 (7 pp.).
DORA PSI
Rochman D, Koning AJ, Sublet JC, Fleming M, Bauge E, Hilaire S, et al.
The TENDL library: hope, reality and future
In: Plompen A, Hambsch F-J, Schillebeeckx P, Mondelaers W, Heyse J, Kopecky S, et al., eds. ND 2016: international conference on nuclear data for science and technology. Vol. 146. EPJ web of conferences. sine loco: EDP Sciences; 2017:02006 (5 pp.). https://doi.org/10.1051/epjconf/201714602006
DORA PSI
Rýdl A, Lind T, Fernandez-Moguel L
Modeling of fission roduct scrubbing in experiments and in integral severe accident scenarios
Presented at: 8th European review meeting on severe accident research (ERMSAR 2017); May 16-18, 2017; Warsaw, Poland.
DORA PSI
Siefman DJ, Hursin M, Grimm P, Pautz A
Case study of data assimilation methods with the LWR-Proteus Phase II experimental campaign
In: Proceedings of the international conference on mathematics & computational methods applied to nuclear science & engineering (M&C 2017). Daejeon: Korean Nuclear Society; 2017:(10 pp.).
DORA PSI
Sjöstrand H, Conroy S, Helgesson P, Hernandez SA, Koning A, Pomp S, et al.
Propagation of nuclear data uncertainties for fusion power measurements
In: Plompen A, Hambsch F-J, Schillebeeckx P, Mondelaers W, Heyse J, Kopecky S, et al., eds. ND 2016: international conference on nuclear data for science and technology. Vol. 146. EPJ web of conferences. sine loco: EDP Sciences; 2017:02034 (4 pp.). https://doi.org/10.1051/epjconf/201714602034
DORA PSI
Szogradi M, Janasz F, Ki-Yong C
Reflux condensation with various non-condensable gases
In: Proceedings of the 3nd World congress on Mechanical, Chemical, and Material Engineering, MCM. Vol. 168. Proceedings of the World Congress on Mechanical, Chemical, and Material Engineering. Optica Publishing Group; 2017:186 (8 pp.). https://doi.org/10.11159/htff17.168
DORA PSI

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2016

Albiol T, Herranz L, Riera E, Dalibart C, Lind T, Del Corno A, et al.
Preliminary insights from the PASSAM project: investigation on enhancement of source term mitigation
In: Proceedings of the 11th international topical meeting on nuclear reactor thermal hydraulics, operation and safety (NUTHOS-11). La Grange Park: American Nuclear Society; 2016:N11P0580 (14 pp.).
DORA PSI
Andreani M, Daqiang Y, Gaikwad AJ, Ganju S, Gera B, Grigoryev S, et al.
Synthesis of a blind CFD benchmark exercise based on a test in the PANDA facility addressing the stratification erosion by a vertical jet in presence of a flow obstruction
In: Computational fluid dynamics for nuclear reactor safety applications-6 (CFD4NRS-6). Workshop proceedings. Paris: OECD; NEA; 2016:(13 pp.).
DORA PSI
Aounallah Y
Simulations of level-swell experiments with TRACE
Presented at: 11th international topical meeting on nuclear reactor thermal hydraulics, operation and safety (NUTHOS-11); October 9-13, 2016; Gyeongju, Korea.
DORA PSI
Bocharov D, Krack M, Kalinko A, Purans J, Rocca F, Ali SE, et al.
Ab initio molecular dynamics simulations of the Sc K-edge EXAFS of scandium trifluoride
In: Grunwaldt J-D, Hagelstein M, Rothe J, eds. 16th international conference on X-ray absorption fine structure (XAFS16). Vol. 712. Journal of physics: conference series. Bristol, Philadelphia: IOP Publishing Ltd; 2016:012009 (4 pp.). https://doi.org/10.1088/1742-6596/712/1/012009
DORA PSI
Bocharov D, Chollet M, Krack M, Bertsch J, Grolimund D, Martin M, et al.
Interpretation of the U L₃-edge EXAFS in uranium dioxide using molecular dynamics and density functional theory simulations
In: 16th international conference on X-ray absorption fine structure (XAFS16). Vol. 712. Journal of physics: conference series. Bristol, Philadelphia: IOP Publishing Ltd; 2016:12091 (4 pp.). https://doi.org/10.1088/1742-6596/712/1/012091
DORA PSI
Bykov V, Vasiliev A, Ferroukhi H, Pautz A
Solution of the BEAVRS benchmark using CASMO-5 / SIMULATE-5 code sequence
In: Physics of reactors 2016 (PHYSOR 2016). Unifying theory and experiments in the 21st century. LaGrange Park, IL, USA: American Nuclear Society; 2016:1960-1968.
DORA PSI
Chionis D, Dokhane A, Ferroukhi H, Pautz A
On causality analysis of nuclear reactor noise using partial directed coherence
In: Physics of reactors 2016 (PHYSOR 2016). Unifying theory and experiments in the 21st century. LaGrange Park, IL, USA: American Nuclear Society; 2016:1162-1171.
DORA PSI
Clifford I, Zerkak O, Pautz A, Yao H, Freixa J
System code validation series based on a consistent plant nodalisation of the ROSA/LSTF integral test facility using TRACE v5.0 Patch 4
Presented at: 11th international topical meeting on nuclear reactor thermal hydraulics, operation and safety (NUTHOS-11); October 9-13, 2016; Gyeongju, Korea.
DORA PSI
Cozzo C, Epiney A, Canepa S, Ferroukhi H, Zerkak O, Khvostov G, et al.
Full core LOCA analysis for BWR/6 - methodology and first results
In: Top Fuel 2016. LWR fuels with enhanced safety and performance. LaGrange Park, IL, USA: American Nuclear Society; 2016:1135-1144.
DORA PSI
Degueldre C, Fiorina C
The proto-Earth geo-reactor: a thorium reactor?
In: Revol J-P, Bourquin M, Kadi Y, Lillestol E, de Mestral J-C, Samec K, eds. Thorium energy for the world. Proceedings of the ThEC13 conference, CERN, globe of science and innovation, Geneva, Switzerland, October 27-31, 2013. Cham: Springer; 2016:415-416. https://doi.org/10.1007/978-3-319-26542-1
DORA PSI
Dehbi A, Han F, Kalilainen J
Large Eddy Simulations of flow inside a cubical differentially heated cavity under realistic boundary conditions
In: Computational fluid dynamics for nuclear reactor safety-5 (CFD4NRS-5). Workshop proceedings. Paris: OECD; 2016:(13 pp.).
DORA PSI
Dehbi A, Kalilainen J
Large Eddy Simulations of free convection particle transport inside cavities at Rayleigh numbers up to 10¹⁰
In: Computational fluid dynamics for nuclear reactor safety applications-6 (CFD4NRS-6). Workshop proceedings. Paris: OECD; NEA; 2016:(16 pp.).
DORA PSI
Dokhane A, Leray O, Rochman D, Ferroukhi H, Pautz A, Grandi G
Validation of SIMULATE-3K against SPERT-III RIA experiments with quantification of nuclear data uncertainties
In: Physics of reactors 2016 (PHYSOR 2016). Unifying theory and experiments in the 21st century. LaGrange Park, IL, USA: American Nuclear Society; 2016:3803-3812.
DORA PSI
Fei T, Vezzoni B, Marchetti M, van Rooijen WFG, Zhang Y
Neutronics benchmark for EBR-II shutdown heat removal test SHRT-45R
In: Physics of reactors 2016 (PHYSOR 2016). Unifying theory and experiments in the 21st century. LaGrange Park, IL, USA: American Nuclear Society; 2016:221-230.
DORA PSI
Grimm P, Hursin M, Perret G, Siefman D, Ferroukhi H
CASMO-5 analysis of reactivity worths of burnt PWR fuel samples measured in LWR-proteus PHASE II
In: Physics of reactors 2016 (PHYSOR 2016). Unifying theory and experiments in the 21st century. LaGrange Park, IL, USA: American Nuclear Society; 2016:2518-2527.
DORA PSI
Halouane Y, Dehbi A
Comparison of hydrogen flame acceleration predictions using the Eddy-Dissipation and the Turbulent Flame Closure
In: Computational fluid dynamics for nuclear reactor safety applications-6 (CFD4NRS-6). Workshop proceedings. Paris: OECD; NEA; 2016:(15 pp.).
DORA PSI
Hursin M, Siefman D, Perret G, Grimm P, Pautz A
Verification of the new implementations in SHARK-X for reactivity coefficients and relative reactivity worth UQ
In: Physics of reactors 2016 (PHYSOR 2016). Unifying theory and experiments in the 21st century. LaGrange Park, IL, USA: American Nuclear Society; 2016:674-683.
DORA PSI
Jacquemain D, Albiol T, Dickinson S, Herranz L-E, Funke F, Glowa G, et al.
Conclusion of the international OECD/NEA-NUGENIA iodine workshop
In: Proceedings of the 11th international topical meeting on nuclear reactor thermal hydraulics, operation and safety (NUTHOS-11). La Grange Park: American Nuclear Society; 2016:N11PA0625 (20 pp.).
DORA PSI
Kalilainen J, Prasser H-M, Lind T, Krepel J, Schenler W
Recent research activities on high temperature pebble bed reactors at PSI
In: 2016 international topical meeting on high temperature reactor technology (HTR 2016). Illinois: American Nuclear Society; 2016:135-140.
DORA PSI
Krepel J, Hombourger B, Bykov V, Fiorina C, Mikityuk K, Pautz A
Paul Scherrer Institute's studies on advanced molten salt reactor fuel cycle options
In: Revol J-P, Bourquin M, Kadi Y, Lillestol E, de Mestral J-C, Samec K, eds. Thorium energy for the world. Proceedings of the ThEC13 conference, CERN, globe of science and innovation, Geneva, Switzerland, October 27-31, 2013. Cham: Springer; 2016:185-192. https://doi.org/10.1007/978-3-319-26542-1_29
DORA PSI
Krepel J, Mikityuk K, Pautz A
The EQL0D procedure for fuel cycle studies in molten salt reactor
In: ICAPP 2016: Proceedings of the International Congress on Advances in Nuclear Power Plants 2016. ; 2016.
DORA PSI
Lamirand V, Hursin M, Frajtag P, Pautz A, Perret G, Pakari O
Future experimental programmes in the CROCUS reactor
In: Conference proceedings. Berlin, Germany. 13-17 March 2016. European research reactor conference 2016. Bruessels, Belgium: European Nuclear Society; 2016:284-291.
DORA PSI
Leray O, Fiorito L, Rochman D, Ferroukhi H, Pautz A, Stankovskiy A, et al.
Comparison of fission yield perturbation methodologies on nuclide composition for a PWR UO2 fuel assembly
In: Physics of reactors 2016 (PHYSOR 2016). Unifying theory and experiments in the 21st century. LaGrange Park, IL, USA: American Nuclear Society; 2016:1669-1680.
DORA PSI
Li J, Rochman D, Herrero J, Ferrouki H, Vasiliev A, Pautz A
Towards analysis of the bowing effect on burnt nuclear fuel compositions using SERPENT
Presented at: American Nuclear Society 2016 student conference; March 31 - April 3, 2016; University of Wisconsin, Madison, USA.
DORA PSI
Lind T, Beghi I, Opilik L, Suckow D
The effect of thermal-hydraulic conditions on iodine retention in a wet scrubber of the FCVS
In: Proceedings of the 11th international topical meeting on nuclear reactor thermal hydraulics, operation and safety (NUTHOS-11). La Grange Park: American Nuclear Society; 2016:N11P1234 (12 pp.).
DORA PSI
Mignot G, Dupont J, Paladino D, Prasser H-M
Containment thermal-hydraulic experiment and potential for severe accident studies in the LINX facility
Presented at: 11th international topical meeting on nuclear reactor thermal hydraulics, operation and safety (NUTHOS-11); October 9-13, 2016; Gyeongju, Korea.
DORA PSI
Mikityuk K
Fast reactor physics
In: Revol J-P, Bourquin M, Kadi Y, Lillestol E, de Mestral J-C, Samec K, eds. Thorium energy for the world. Proceedings of the ThEC13 conference, CERN, globe of science and innovation, Geneva, Switzerland, October 27-31, 2013. Cham: Springer; 2016:215-221. https://doi.org/10.1007/978-3-319-26542-1_33
DORA PSI
Mukin R, Zerkak O, Pautz A
Modeling and analysis of selected OECD PKL3 Station-Blackout experiments using TRACE
Presented at: 11th international topical meeting on nuclear reactor thermal hydraulics, operation and safety (NUTHOS-11); October 9-13, 2016; Gyeongju, Korea.
DORA PSI
Mukin R, Dehbi A
Simulation of flow on the secondary side of a steam generator bundle
In: Computational fluid dynamics for nuclear reactor safety-5. (CFD4NRS-5). Workshop proceedings. Paris, France: OECD; 2016. https://www.oecd-nea.org/nsd/csni/cfd/.
DORA PSI
Paranjape S, Kapulla R, Mignot G, Paladino D
Erosion of a helium layer due to the flow resulting from the interaction of a steam jet with a flow obstruction in a large vessel
Presented at: 11th international topical meeting on nuclear reactor thermal hydraulics, operation and safety (NUTHOS-11); October 9-13, 2016; Gyeongju, Korea.
DORA PSI
Pelloni S
A progressive incremental adjustment methodology for cross-section and variance/covariance data adjustment for fast-spectrum systems
Presented at: PHYSOR 2016: unifying theory and experiments in the 21st century; May 1-5, 2016; Sun Valley, ID, USA.
DORA PSI
Perret G
Delayed neutron fraction and prompt decay constant measurement in the Minerve reactor using the PSI instrumentation
In: 2015 4th international conference on advancements in nuclear instrumentation measurement methods and their applications (ANIMMA). 2015 4th international conference on advancements in nuclear instrumentation measurement methods and their applications (ANIMMA). Danvers: IEEE; 2016:8 pp. https://doi.org/10.1109/ANIMMA.2015.7465533
DORA PSI
Perret G, Vlassopoulos E, Hursin M, Pautz A
Toward reanalysis of the tight-pitch HCLWR-PROTEUS Phase II experiments
In: Serot O, ed. Wonder-2015 – 4th international workshop on nuclear data evaluation for reactor applications. Vol. 111. EPJ web of conferences. Les Ulis Cedex A, France: EDP Sciences; 2016:11006 (9 pp.). https://doi.org/10.1051/epjconf/201611111006
DORA PSI
Puragliesi R, Zerkak O, Pautz A
Influence of URANS turbulence models on in-vessel flow mixing during cold leg accumulator injection
Presented at: 11th international topical meeting on nuclear reactor thermal hydraulics, operation and safety (NUTHOS-11); October 9-13, 2016; Gyeongju, Korea.
DORA PSI
Rahman S, Karanki DR, Wicaksono D, Zerkak O, Dang VN
Evaluation of deterministic sampling for uncertainty quantification in a probabilistic accident analysis model
Presented at: 11th international topical meeting on nuclear reactor thermal hydraulics, operation and safety (NUTHOS-11); October 9-13, 2016; Gyeongju, Korea.
DORA PSI
Rais A, Hursin M, Perret G, Pautz A
Experimental validation of control rod reactivity worth and fission rate distributions for the CROCUS Reactor
In: Physics of reactors 2016 (PHYSOR 2016). Unifying theory and experiments in the 21st century. Vol. 6. LaGrange Park, IL, USA: American Nuclear Society; 2016:3874-3883.
DORA PSI
Rýdl A, Fernandez-Moguel L, Lind T
Impact of containment venting on source term for Fukushima-like BWR scenarios
Presented at: 11th international topical meeting on nuclear reactor thermal hydraulics, operation and safety (NUTHOS-11); October 9-13, 2016; Gyeongju, Korea.
DORA PSI
Savelli R, Vasiliev A, Ferroukhi H, Pautz A
Extention of PSI FNF modeling methodology validation using BWR dosimetry data
Presented at: American Nuclear Society 2016 student conference; March 31 - April 3, 2016; University of Wisconsin, Madison, USA.
DORA PSI
Wicaksono D, Zerkak O, Pautz A
Bayesian calibration of thermal-hydraulics model with time-dependent output
Presented at: 11th international topical meeting on nuclear reactor thermal hydraulics, operation and safety (NUTHOS-11); October 9-13, 2016; Gyeongju, Korea.
DORA PSI

Scaling And Cfd Modelling Of The Pool Experiments With Spargers Performed In The Panda Facility
Ignacio Gallego-Marcos, Walter Villanueva, Pavel Kudinov, Ralf Kapulla, Sidharth Paranjape, Domenico Paladino
Nuthos-11: Proceedings Of The 11th International Topical Meeting On Nuclear Reactor Thermal-Hydraulics, Operation And Safety (Oct 9-13, 2016, Gyeongju, Korea) Nuthos-11, 1 (2016).

Simulations Of Level-Swell Experiments With Trace
Y. Aounallah
Nuthos-11, Gyeongju, Korea, October 9-13, 2016

The Tendl Library: Hope, Reality And Future
D. Rochman, A.J. Koning, J.Ch. Sublet, M. Fleming, E. Bauge, S. Hilaire, P. Romain, B. Morillon, H. Duarte, S. Goriely, S.C. Van Der Marck, H. SjöStrand, S. Pomp, N. Dzysiuk, O. Cabellos, H. Ferroukhi, A. Vasiliev
Proc. Nuclear Data 2016, Bruges, Belgium, September 11-16, 2016

Impact Of Nuclear Data Uncertainty On Safety Calculations For Spent Nuclear Fuel Geological Disposal
J.J. Herrero, D. Rochman, O. Leray, A. Vasiliev, M. Pecchia, H. Ferroukhi, S. Caruso
Proc. Nuclear Data 2016, Bruges, Belgium, September 11-16, 2016 (Epj Web of Conferences 146, 09028, 2017)

Impact Of Implicit Effects On Uncertainties And Sensitivities Of The Doppler Coefficient Of A Lwr Pin Cell
M. Hursin, O. Leray, G.Perret, A.Pautz, F. Bostelmann, A. Aures, W. Zwermann
Proc. Nuclear Data 2016, Bruges, Belgium, September 11-16, 2016 (Epj Web of Conferences 146, 09034, 2017)

Fission Yield Covariances For Jeff: A Bayesian Monte Carlo Method
O. Leray, D. Rochman, M. Fleming, J-C. Sublet, A. Koning, A. Vasiliev, H. Ferroukhi
Proc. Nuclear Data 2016, Bruges, Belgium, September 11-16, 2016 (Epj Web of Conferences 146, 09023, 2017)

Comparative Study Of Casmo-5/Simulate-5 And Ntracer For Epr Core Analyses
S. Canepa, H. Ferroukhi, R. Min, H.G. Joo
Icapp 2016, San Francisco, Ca, Usa, April 17-20, 2016

Towards Analysis Of The Bowing Effect On Burnt Nuclear Fuel Compositions Using Serpent
J. Li, D. Rochman, J. Herrero, H. Ferroukhi, A. Vasiliev, A. Pautz
American Nuclear Society 2016 Student Conference, University of Wisconsin, Madison, Usa, March 31-April 3, 2016

Extention Of Psi Fnf Modeling Methodology Validation Using Bwr Dosimetry Data
R. Savelli, A. Vasiliev, H. Ferroukhi, A. Pautz
American Nuclear Society 2016 Student Conference, University of Wisconsin, Madison, Usa, March 31-April 3, 2016

The effect of thermal-hydraulic conditions on iodine retention in a wet scrubber of the FCVS
T.M. Lind, I. Beghi, L. Opilik, D.J. Suckow
11^th NUTHOS, Gyeongju, Korea

Thermal-hydraulic evaluation of the system code TRACE/PARCS using different sets of cross-sections
P. Papadopoulos, A. Sehkri, P. Hidalga, G. Verdu
11^th NUTHOS, Gyeongju, Korea

Preliminary insights from the PASSAM project: investigation on enhancement of source term mitigation
T. Albiol, L.-E. Herranz, E. Riera, C. Dalibart, T.M. Lind, A. del Corno, T. Kärkelä, N. Losch, B. Azambre
11^th NUTHOS, Gyeongju, Korea

Conclusion of the International OECD/NEA-NUGENIA Iodine workshop
D. Jacquemain, T. Albiol, S. Dickinson, L.-E. Herranz, F. Funke, G. Glowa, S. Gupta, H. Hoshi, T. Kärkelä, M. Kissane, T.M. Lind, M. Salay, J.-H. Song, J.-P. van Dorsselaere
11^th NUTHOS, Gyeongju, Korea

Comparison of Hydrogen Flame Acceleration Predictions using the Eddy-Dissipation and the Turbulent Flame Closure
Y. Halouane, A. Dehbi
6^th CFD4NRS, Boston, USA

Large Eddy Simulation of Free Convection Particle Transport Inside Cavities at Rayleigh Numbers up to 10¹⁰
A. Dehbi, J. Kalilainen
6^th CFD4NRS, Boston, USA

Determination of the Decontamination Factor in Two-Phase Flows using Wire-Mesh Sensors
P. Papadopoulos, K. Baur, T.M. Lind, H.-M. Prasser
SWINTH, Livorno, Italy

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2015

Aufiero M, Fiorina C, Laureau A, Rubiolo P, Valtavirta V
Serpent-OpenFOAM coupling in transient mode: simulation of a Godiva prompt critical burst
In: Mathematics and computations, supercomputing in nuclear applications and Monte Carlo international conference (M&C and SNA and MC 2015). Mathematics and computations, supercomputing in nuclear applications and Monte Carlo international conference (M&C+SNA+MC 2015). LaGrange Park, IL, USA: American Nuclear Society; 2015:1995-2006.
DORA PSI
Bortot S, Alvarez-Velarde F, Fridman E, Garcia Cruzado I, Garcia Herranz N, López D, et al.
European benchmark on the ASTRID-like low-void-effect core characterization: neutronic parameters and safety coefficients
In: Proceedings of 2015 international congress on advances in nuclear power plants (ICAPP 2015). Paris, France: SFEN; 2015:668-676. https://www.sfen.org/.
DORA PSI
Brankov V, Khvostov G, Mikityuk K, Pautz A, Restani R, Abolhassani S, et al.
Modeling of axial distribution of released fission gas in KKL BWR fuel rods during base irradiation
In: TopFuel 2015. Reactor fuel performance. Conference proceedings. Part 1. Brussels: European Nuclear Society; 2015:609-619.
DORA PSI
Bubelis E, Schikorr M, Frogheri M, Mansani L, Bandini G, Burgazzi L, et al.
LFR safety approach and main ELFR safety analysis results
In: Track 3 - safety. Vienna: International Atomic Energy Agency; 2015:IAEA-CN-199/297 (10 pp.).
DORA PSI
Bykov V, Volmert B, Pautz A
Enhancement and Validation of BWR MCNP Activation Simulations for Swiss Decommissioning Planning
Presented at: 2015 American Nuclear Society Student Conference; April 9-11, 2015; College Station, TX, USA.
DORA PSI
Canepa S, Krack M, Ferroukhi H, Pautz A
Scalability benchmarking methodology for hybrid parallel core calculations with the code nTRACER
In: Mathematics and computations, supercomputing in nuclear applications and Monte Carlo international conference (M&C and SNA and MC 2015). LaGrange Park, IL, USA: American Nuclear Society; 2015:2819-2831.
DORA PSI
Chionis D, Hofer K, Pautz A
Peak cladding temperature prediction and assessment for the Leibstadt NPP using SIMULATE-3K
In: 2015 ANS student conference. Powering tomorrow together. La Grange Park: American Nuclear Society; 2015:(6 pp.).
DORA PSI
Chollet M, Krsjak V, Cozzo C, Bertsch J
Positron annihilation spectroscopy study of lattice defects in non-irradiated doped and un-doped fuels
In: TopFuel 2015. Reactor fuel performance. Conference proceedings. Part 1. Brussels: European Nuclear Society; 2015:502-509.
DORA PSI
Chollet M, Krack M, Kuzmin A, Bertsch J, Grolimund D, Martin M
Theoretical modelling of pristine and chromium-doped UO₂
Presented at: E-MRS 2015; May 11-15, 2015; Lille, France.
DORA PSI
Clifford I, Vasiliev A, Zerkak O, Ferroukhi H, Pautz A
Computational fluid dynamics analysis of the fluid flow and heat transfer in the core bypass region of a PWR
In: 16th international topical meeting on nuclear reactor thermal hydraulics (NURETH-16). LaGrange Park, IL, USA: American Nuclear Society; 2015:7806-7819.
DORA PSI
Dokhane A, Zerkak O, Ferroukhi H, Gajev I, Judd J, Kozlowski T
TRACE/SIMULATE-3K analysis of the NEA/OECD Oskarshamn-2 stability benchmark
In: 16th international topical meeting on nuclear reactor thermal hydraulics (NURETH-16). LaGrange Park, IL, USA: American Nuclear Society; 2015:4757-4770.
DORA PSI
Epiney A, Canepa S, Zerkak O, Ferroukhi H
Towards a consolidated approach for the validation of plant system codes and models: case study for a BWR fast depressurisation event
In: 16th international topical meeting on nuclear reactor thermal hydraulics (NURETH-16). LaGrange Park, IL, USA: American Nuclear Society; 2015:2157-2170.
DORA PSI
Fernandez-Moguel L, Rydl A, Jaeckel B
Analysis of Fukushima Daiichi NPP unit 3 with Melcor_2.1
In: 16th international topical meeting on nuclear reactor thermal hydraulics (NURETH-16). LaGrange Park, IL, USA: American Nuclear Society; 2015:6401-6411.
DORA PSI
Fiorina C, Mikityuk K
Application of the new GeN-Foam multi-physics solver to the European Sodium Fast Reactor and verification against available codes
In: Proceedings of 2015 international congress on advances in nuclear power plants (ICAPP 2015). Paris, France: SFEN; 2015:2017-2024. https://www.sfen.org/.
DORA PSI
Fiorina C, Mikityuk K, Pautz A
GeN-Foam: a novel multi-physics solver for reactor analysis - status and ongoing developments
In: Federici G, Corradini ML, Klein AC, Uckan NA, Rimpault G, Cacuci DG, et al., eds. Proceedings of the American Nuclear Society. Vol. 113. Transactions of the American Nuclear Society. La Grange Park: American Nuclear Society; 2015:1132-1134. https://www.ans.org/pubs/transactions/article-38067/.
DORA PSI
Ghasabyan L, Mikityuk K, Krepel J, Pelloni S
Use of Serpent Monte-Carlo code for development of 3D full-core models of Gen-IV fast spectrum reactors and preparation of safety parameters/cross-section data for transient analysis
In: Track 7 - experiments and simulation. Vienna: International Atomic Energy Agency; 2015:(10 pp.).
DORA PSI
Grasso G, Döderlein C, Tučekc K, Mikityuk K, Manni F, Gugiu D
A core design approach aimed at the sustainability and intrinsic safety of the European Lead-cooled Fast Reactor
In: Track 1 - designs. Vienna: International Atomic Energy Agency; 2015:97-106.
DORA PSI
Grasso G, Petrovic C, Mikityuk K, Mattioli D, Manni F, Gugiu D
Demonstrating the effectiveness of the European LFR concept: the ALFRED core design
In: Track 1 - designs. Vienna: International Atomic Energy Agency; 2015:IAEA-CN-199/312 (10 pp.).
DORA PSI
Herrero JJ, Pecchia M, Ferroukhi H, Canepa S, Vasiliev A, Caruso S
Computational scheme for burnup credit applied to long term waste disposal
In: ICNC 2015 - international conference on nuclear criticality safety. LaGrange Park, IL, USA: American Nuclear Society; 2015:1783-1791.
DORA PSI
Hombourger B, Pautz A, Krepel J, Mikityuk K
Fuel cycle analysis of a Molten Salt Reactor for Breed-and-Burn mode
In: Proceedings of 2015 international congress on advances in nuclear power plants (ICAPP 2015). Paris, France: SFEN; 2015:910-916.
DORA PSI
Hursin M, Joo HG, Downar TJ
Assessment of thermal hydraulic feedbacks effects during modeling of a RIA using direct whole core transport solution
In: Mathematics and computations, supercomputing in nuclear applications and Monte Carlo international conference (M&C and SNA and MC 2015). LaGrange Park, IL, USA: American Nuclear Society; 2015:2394-2405.
DORA PSI
Hursin M, Rossinelli L, Ferroukhi H, Pautz A
BWR full core analysis with SERPENT/SIMULATE-3 hybrid stochastic/determinstic code sequence
In: Mathematics and computations, supercomputing in nuclear applications and Monte Carlo international conference (M&C and SNA and MC 2015). LaGrange Park, IL, USA: American Nuclear Society; 2015:1794-1806.
DORA PSI
Kapulla R, Kelm S, Mignot G, Paranjape S, Paladino D
Experimental and numerical results for the erosion dynamics of a vertical helium-air jet interacting with a helium rich layer
In: Proceedings of ICAPP 2015. Vol. 49. INIS. Paris: SFEN; 2015:15242 (16 pp.). https://inis.iaea.org/search/search.aspx?num=10&orig_q=RN%3a49005001&lang=en-US&login=false&user=External&src=&sort=date:D:L:d1&sortorder=ascending&search-option=Everywhere&q=+inmeta:ConferenceTitle%3DICAPP%25202015%253A%2520Nuclear%2520Innovations%2.
DORA PSI
Krepel J, Fiorina C, Mikityuk K
Comparison of several recycling strategies and relevant fuel cycles for molten salt reactor
In: Proceedings of 2015 international congress on advances in nuclear power plants (ICAPP 2015). Paris, France: SFEN; 2015.
DORA PSI
Krepel J, Pelloni S, Bortot S, Panadero AL, Mikityuk K
Mapping of sodium void worth and Doppler effect for sodium-cooled fast reactor
In: Proceedings of 2015 international congress on advances in nuclear power plants (ICAPP 2015). Paris, France: SFEN; 2015:677-684. https://www.sfen.org/.
DORA PSI
Krepel J, Brankov V, Mikityuk K
Selection of initial fuel composition for the ESFR core based on the knowledge of its equilibrium closed cycle parameters
In: Track 8 - deployment and scenarios. Vienna: International Atomic Energy Agency; 2015:(9 pp.).
DORA PSI
Kriventsev V, Rineiski A, Pfrang W, Perez-Martin S, Mikityuk K, Khvostov G
Benchmark on behavior of MOX fuel pin under irradiation at nominal power in sodium fast reactor
In: TopFuel 2015. Reactor fuel performance. Conference proceedings. Part 2. Brussels: European Nuclear Society; 2015:550-559.
DORA PSI
Leray O, Pecchia M, Vasiliev A, Ferroukhi H, Pautz A, Perrier H
Development, verification and test application of a hybrid CASMO-5/SERPENT depletion scheme
In: Mathematics and computations, supercomputing in nuclear applications and Monte Carlo international conference (M&C and SNA and MC 2015). LaGrange Park, IL, USA: American Nuclear Society; 2015:1781-1793.
DORA PSI
Mala P, Canepa S, Ferroukhi H, Pautz A
Preparation of pin-by-pin nuclear libraries with superhomogenization method for nTRACER and DORT core calculations
In: Mathematics and computations, supercomputing in nuclear applications and Monte Carlo international conference (M&C and SNA and MC 2015). LaGrange Park, IL, USA: American Nuclear Society; 2015:775-786.
DORA PSI
Mignot G, Paranjape S, Kapulla R, Paladino D
Performance of hydrogen mitigation systems for a scaled accident scenario: overview of ERCOSAM project experimental results for the PANDA facility
In: 16th international topical meeting on nuclear reactor thermal hydraulics (NURETH-16). LaGrange Park, IL, USA: American Nuclear Society; 2015:5456-5469.
DORA PSI
Mikityuk K, Schikorr M
New transient analysis of the Superphenix start-up tests
In: Track 9 - decommissioning. Vienna: International Atomic Energy Agency; 2015:IAEA-CN-199/297155 (10 pp.).
DORA PSI
Mikityuk K, Perkó Z, Girardin G
Reactivity effect of steam/water ingress in Generation-IV Gas-cooled Fast Reactor core
In: Track 3 - safety. Vienna: International Atomic Energy Agency; 2015:(7 pp.).
DORA PSI
Paladino D, Kapulla R, Mignot G, Paranjape S
Combined effects of cooler and spray activation on the hydrogen distribution in the presence of a jet flow
In: 16th international topical meeting on nuclear reactor thermal hydraulics (NURETH-16). Vol. 2. American Nuclear Society; 2015:1502-1515.
DORA PSI
Paladino D, Kiselev A
Main outcomes from the EURATOM-ROSATOM ERCOSAM SAMARA parallel projects for hydrogen safety of LWR
In: Proceedings of ICAPP 2015. Vol. 49. INIS. Paris: SFEN; 2015:15357 (11 pp.). https://inis.iaea.org/search/search.aspx?orig_q=RN:49004920.
DORA PSI
Paranjape S, Kapulla R, Mignot G, Paladino D
Parametric study on density stratification erosion caused by a horizontal steam jet interacting with a vertical plate obstruction
In: 16th international topical meeting on nuclear reactor thermal hydraulics (NURETH-16). LaGrange Park, IL, USA: American Nuclear Society; 2015:4490-4503.
DORA PSI
Park S, Fernandez-Moguel L, Prasser H-M, Birchley J, Steinbrück M, Seifert H-J
Effect of nitriding during an air ingress scenario
In: TopFuel 2015. Reactor fuel performance. Conference proceedings. Part 2. Brussels: European Nuclear Society; 2015:380-390.
DORA PSI
Pecchia M, Herrero JJ, Ferroukhi H, Vasiliev A, Canepa S, Pautz A
COMPLINK: a versatile tool for automatizing the representation of material data in MCNP models
In: ICNC 2015 - international conference on nuclear criticality safety. LaGrange Park, IL, USA: American Nuclear Society; 2015:513-522.
DORA PSI
Pelloni S, Aufiero M, Bortot S, Krepel J, Mikityuk K, Panadero AL, et al.
Sodium void map preparation for the safety analysis of Sodium-cooled Fast Reactors by using the Monte Carlo code Serpent
In: Proceedings of 2015 international congress on advances in nuclear power plants (ICAPP 2015). Paris, France: SFEN; 2015. https://www.sfen.org/.
DORA PSI
Poette C, Guedeney P, Stainsby R, Mikityuk K, Knol S
Gas cooled fast reactors: recent advances and prospects
In: Track 1 - designs. Vienna: International Atomic Energy Agency; 2015:(10 pp.).
DORA PSI
Puragliesi R, Zerkak O, Pautz A, Zhou Q
Assessment of OpenFOAM CFD toolbox for gravity driven mixing flows in a Reactor Pressure Vessel
In: 16th international topical meeting on nuclear reactor thermal hydraulics (NURETH-16). LaGrange Park, IL, USA: American Nuclear Society; 2015:952-965.
DORA PSI
Rahman S, Karanki DR, Epiney A, Zerkak O, Dang VN
Ranking of uncertain parameters for dynamic event tree analysis: a case study based on a Station Black Out scenario
In: 16th international topical meeting on nuclear reactor thermal hydraulics (NURETH-16). LaGrange Park, IL, USA: American Nuclear Society; 2015:5734-5747.
DORA PSI
Rineiski A, Vezzoni B, Zhang D, Marchetti M, Gabrielli F, Maschek W, et al.
ESFR core optimization and uncertainty studies
In: Track 1 - designs. Vienna: International Atomic Energy Agency; 2015:265-274.
DORA PSI
Rýd A, Jäckel B, Klügel J-U, Steiner P
Melt-concrete interface heat transfer models and coolability models: PWR analyses with MELCOR/CORCON and CORQUENCH
In: 16th international topical meeting on nuclear reactor thermal hydraulics (NURETH-16). LaGrange Park, IL, USA: American Nuclear Society; 2015:484-498.
DORA PSI
Vasile A, Wahide C, Latge C, Chauvin N, Baeten P, Schyns M, et al.
The European project ESNII Plus
In: Proceedings of 2015 international congress on advances in nuclear power plants (ICAPP 2015). Paris, France: SFEN; 2015:928-936. https://www.sfen.org/.
DORA PSI
Vasiliev A, Rochman D, Zhu T, Pecchia M, Ferroukhi H, Pautz A
Towards application of neutron cross-section uncertainty propagation capability in the criticality safety methodology
In: ICNC 2015 - international conference on nuclear criticality safety. LaGrange Park, IL, USA: American Nuclear Society; 2015:606-615.
DORA PSI
Vrban B, Čerba Š, Lüley J, Haščík J, Nečas V, Pelloni S
Investigation of the coupled reactivity effects of the movable reflector and safety control rods in the GFR
In: Track 3 - safety. Vienna: International Atomic Energy Agency; 2015:144 (11 pp.).
DORA PSI
Wicaksono D, Zerkak O, Pautz A
A methodology for global sensitivity analysis of transient code output applied to a reflood experiment model using TRACE
In: 16th international topical meeting on nuclear reactor thermal hydraulics (NURETH-16). LaGrange Park, IL, USA: American Nuclear Society; 2015:4862-4879.
DORA PSI
Zanetti M, Cammi A, Luzzi L, Křepel J, Mikityuk K
Extension of the FAST code system for the modelling and simulation of MSR dynamics
In: Proceedings of ICAPP 2015. Paris, France: SFEN; 2015:883-890.
DORA PSI
Zboray R, Dangendorf V, Mor I, Tittelmeier K, Bromberger B, Prasser H-M
Time-resolved fast neutron radiography of air-water two-phase flows
In: Lehmann EH, Kaestner AP, Mannes D, eds. Proceedings of the 10th world conference on neutron radiography (WCNR-10) Grindelwald, Switzerland October 5-10, 2014. Vol. 69. Physics procedia. sine loco: Elsevier; 2015:551-555. https://doi.org/10.1016/j.phpro.2015.07.078
DORA PSI
Zhang Y, Mikityuk K
Validation of the Serpent and TRACE codes using the SHRT-17 and SHRT-45R loss-of-flow tests performed in the EBR-II reactor
In: Proceedings of 2015 international congress on advances in nuclear power plants (ICAPP 2015). Paris, France: SFEN; 2015:495-503. https://www.sfen.org/.
DORA PSI

Peak Cladding Temperature Prediction And Assessment For The Leibstadt Npp Using Simulate-3k
D. Chionis, K. Hofer, A.Pautz
Proc. American Nucl. Societ Student Conference 2015, College Station, Tx Texas A&M University, April 9-11, 2015

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2010 - 2014

Aounallah Y
Assessment of TRACE against single-tube post-dryout heat transfer experiments
Presented at: 10th international topical meeting on nuclear thermal-hydraulics, operation and safety (NUTHOS-10); December 14-18, 2014; Okinawa, Japan.
DORA PSI
Bortot S, Pelloni S, Mikityuk K
Methodology assessment for the evaluation of the coolant void worth in Sodium Fast Reactors with a low void effect core design
Presented at: International conference on physics of reactors (PHYSOR 2014); September 28-October 3, 2014; Kyoto, Japan.
DORA PSI
Bykov V, Křepel J, Pautz A
Molten salt fast reactor blanket design and proliferation resistance assessment
In: Proceedings of the 2014 22nd international conference on nuclear engineering (ICONE22). New York: American Society of Mechanical Engineers (ASME); 2014:V005T17A061 (9 pp.). https://doi.org/10.1115/ICONE22-31026
DORA PSI
Clifford I, Zerkak O, Pautz A
Post-test analysis of OECD/NEA ROSA-2 test 4 using TRACE
Presented at: 10th international topical meeting on nuclear thermal-hydraulics, operation and safety (NUTHOS-10); December 14-18, 2014; Okinawa, Japan.
DORA PSI
Dokhane A, Ferroukhi H, Pautz A
Analysis of the OECD/NEA Oskarshamn-2 feedwater transient and stability benchmark with simulate-3K
In: Proceedings of the international conference on physics of reactors (PHYSOR 2014). PHYSOR 2014 – the role of reactor physics toward a sustainable future. ; 2014:1101708 (14 pp.).
DORA PSI
Dupont J, Mignot G, Zboray R, Prasser H-MP
Characterization and validation of the near infrared film thickness profile technique
Presented at: 10th international topical meeting on nuclear thermal-hydraulics, operation and safety (NUTHOS-10); December 14-18, 2014; Okinawa, Japan.
DORA PSI
Dupré A, Vasiliev A, Ferroukhi H, Pautz A
Validation enhancements of the PSI Fast Neutron Fluence computational scheme using operational PWR experimental data
Presented at: American Nuclear Society 2014 student conference; April 3-6, 2014; Pennsylvania.
DORA PSI
Epiney A, Zerkak O, Pautz A
Uncertainty- and sensitivity analysis of COBRA-TF for the simulation of selected OECD/NRC BFBT void experiments
Presented at: 10th international topical meeting on nuclear thermal-hydraulics, operation and safety (NUTHOS-10); December 14-18, 2014; Okinawa, Japan.
DORA PSI
Fiorina C, Mikityuk K, Křepel J
A procedure for the pre-conceptual design of fast reactors and application to a gas-cooled sub-critical transmuter
In: Proceedings of the 2014 22nd international conference on nuclear engineering (ICONE22). New York: American Society of Mechanical Engineers (ASME); 2014:V005T16A001 (9 pp.). https://doi.org/10.1115/ICONE22-30387
DORA PSI
Fiorina C, Aufiero M, Pelloni S, Mikityuk K
A time-dependent solver for coupled neutron-transport thermal-mechanics calculations and simulation of a Godiva prompt-critical burst
In: Proceedings of the 2014 22nd international conference on nuclear engineering (ICONE22). New York: American Society of Mechanical Engineers (ASME); 2014:V004T11A008 (9 pp.). https://doi.org/10.1115/ICONE22-30395
DORA PSI
Fiorina C, Cammi A, Luzzi L, Mikityuk K, Ninokata H, Ricotti ME
Thermal-hydraulics of internally heated molten salts and application to the Molten Salt Fast Reactor
In: 31st UIT (Italian union of thermo-fluid-dynamics) heat transfer conference 2013. Vol. 501. Journal of physics: conference series. Bristol, UK: IOP Publishing; 2014:012030 (10 pp.). https://doi.org/10.1088/1742-6596/501/1/012030
DORA PSI
Grimm P, Perret G, Ferroukhi H
CASMO-4E AND CASMO-5 analysis of the isotopic compositions of the LWR-PROTEUS phase II burnt PWR UO₂ fuel samples
Presented at: International conference on physics of reactors (PHYSOR 2014); September 28-October 3, 2014; Kyoto, Japan.
DORA PSI
Herranz LE, Tardáguila RD, Berschart T, Lind T, Morandi S
Remaining issues in pool scrubbing: major drivers for experimentation within the EU-PASSAM project
In: Proceedings of ICAPP '14. Vol. 2. International congress on advances in nuclear power plants, ICAPP 2014. La Grange Park: American Nuclear Society; 2014:14156 (9 pp.).
DORA PSI
Hombourger BA, Křepel J, Mikityuk K, Pautz A
Parametric lattice study of a graphite-moderated molten salt reactor
In: Proceedings of the 2014 22nd international conference on nuclear engineering (ICONE22). New York: American Society of Mechanical Engineers (ASME); 2014:V005T17A063 (7 pp.). https://doi.org/10.1115/ICONE22-31050
DORA PSI
Hursin M, Ferroukhi H, Pautz A
Neutronic Data Generation for BWR Models, Comparison OF SERPENT and CASMO-5
Presented at: ANS student conference 2014; April 3-6, 2014; University Park, PA, USA.
DORA PSI
Hursin M, Scriven M, Perret G, Grimm P, Pautz A
Pinpower uncertainty quantification of LWR-PROTEUS phase III experiments
Presented at: International conference on physics of reactors (PHYSOR 2014); September 28-October 3, 2014; Kyoto, Japan.
DORA PSI
Hursin M, Siefman D, Rais A, Girardin G, Pautz A
Verification of a reactor physics calculation scheme for the CROCUS reactor
In: 3rd international technical meeting on small reactors. Vol. 1. Toronto, Canada: Canadian nuclear society; 2014. https://infoscience.epfl.ch/record/253153/files/ITSMR_2014.pdf.
DORA PSI
Jaeckel B, Birchley J, Fernandez-Moguel L
Spent fuel pool under severe accident conditions
In: Proceedings of the 2014 22nd international conference on nuclear engineering (ICONE22). New York: American Society of Mechanical Engineers (ASME); 2014:V003T06A029 (7 pp.). https://doi.org/10.1115/ICONE22-30729
DORA PSI
Kapulla R, Mignot G, Paranjape S, Paladino D
Stably stratified helium layer erosion by a vertical buoyant helium-air jet
In: Proceedings of the 2014 international congress on advances in nuclear power plants. La Grange Park: American Nuclear Society; 2014:(23 pp.). https://www.ans.org/store/item-700385/.
DORA PSI
Karanki DR, Zerkak O, Dang VN
Treatment of epistemic and aleatory uncertainties in DET simulations: computational framework with ADS-TRACE
Presented at: 10th international topical meeting on nuclear thermal-hydraulics, operation and safety (NUTHOS-10); December 14-18, 2014; Okinawa, Japan.
DORA PSI
Křepel J, Mikityuk K, Hombourger B, Pautz A, Zanetti M, Aufiero M, et al.
Hybrid spectrum Molten Salt Reactor
Presented at: International conference on physics of reactors (PHYSOR 2014); September 28-October 3, 2014; Kyoto, Japan.
DORA PSI
Křepel J, Bykov V, Mikityuk K, Hombourger B, Fiorina C, Pautz A
Molten salt reactor with simplified fuel recycling and delayed carrier salt cleaning
In: Proceedings of the 2014 22nd international conference on nuclear engineering (ICONE22). New York: American Society of Mechanical Engineers (ASME); 2014:V003T05A015 (11 pp.). https://doi.org/10.1115/ICONE22-30396
DORA PSI
Leray O, Grimm P, Ferroukhi H, Pautz A
Quantification of code, library and cross-section uncertainty effects on the void reactivity coefficient of a BWR UO₂ assembly
Presented at: International conference on physics of reactors (PHYSOR 2014); September 28-October 3, 2014; Kyoto, Japan.
DORA PSI
Leray O, Pecchia M, Vasiliev A, Ferroukhi H, Pautz A
Reactivity benchmark Analysis and Code Reactivity Prediction for a PWR Fuel Assembly
Presented at: ANS student conference 2014; April 3-6, 2014; University Park, PA, USA.
DORA PSI
Leray O, Grimm P, Hursin M, Ferroukhi H, Pautz A
Uncertainty quantification of spent fuel nuclide compositions due to cross sections, decay constants and fission yields
Presented at: International conference on physics of reactors (PHYSOR 2014); September 28-October 3, 2014; Kyoto, Japan.
DORA PSI
Mala P, Canepa S, Ferroukhi H, Pautz A
Effects of advanced radial submeshing methods on pin power reconstruction for an EPR core design
Presented at: International conference on physics of reactors (PHYSOR 2014); September 28-October 3, 2014; Kyoto, Japan.
DORA PSI
Mukin R, Dehbi A
Simulation of a gas jet in the secondary side of a steam generator bundle following a tube rupture sequence
In: Proceedings of the 2014 22nd international conference on nuclear engineering (ICONE22). New York: American Society of Mechanical Engineers (ASME); 2014:V004T10A018 (9 pp.). https://doi.org/10.1115/ICONE22-30517
DORA PSI
Ngayam-Happy RA, Krack M
Radiation damage characterization in non-stoichiometric uranium dioxide by molecular dynamics simulations
In: Caruge D, Calvin C, Diop CM, Malvagi F, Trama J-C, eds. SNA and MC 2013 - joint international conference on supercomputing in nuclear applications and monte carlo. sine loco: EDP Sciences; 2014:01301 (2 pp.). https://doi.org/10.1051/snamc/201401301
DORA PSI
Paladino D, Mignot G, Kapulla R, Paranjape S, Andreani M, Studer E, et al.
OECD/NEA HYMERES project: for the analysis and mitigation of a severe accident leading to hydrogen release into a nuclear plant containment
In: International congress on advances in nuclear power plants (ICAPP 2014). Vol. 2. Illinois: American Nuclear Society (ANS); 2014:1314-1322.
DORA PSI
Paranjape S, Mignot G, Paladino D
Effect of thermal stratification on full cone spray performance in reactor containment for a scaled scenario
In: Proceedings of the 2014 22nd international conference on nuclear engineering (ICONE22). New York: American Society of Mechanical Engineers (ASME); 2014:V02BT09A020 (14 pp.). https://doi.org/10.1115/ICONE22-30755
DORA PSI
Pascal V, Prulhiere G, Vanier M, Fontaine B, Devan K, Chellapandi P, et al.
IAEA benchmark calculations on control rod withdrawal test performed during PHENIX End-Of-Life Experiments – benchmark results and comparisons
Presented at: International conference on physics of reactors (PHYSOR 2014); September 28-October 3, 2014; Kyoto, Japan.
DORA PSI
Pecchia M, Vasiliev A, Ferroukhi H, Pautz A
Updated validation of the PSI criticality safety evaluation methodology using MCNPX2.7 and ENDF/B-VII.1
Presented at: International conference on physics of reactors (PHYSOR 2014); September 28-October 3, 2014; Kyoto, Japan.
DORA PSI
Puragliesi R, Zerkak O, Pautz A
Assessment of CFD uRANS models for buoyancy driven mixing flows based on ROCOM experiments
Presented at: 10th international topical meeting on nuclear thermal-hydraulics, operation and safety (NUTHOS-10); December 14-18, 2014; Okinawa, Japan.
DORA PSI
Rais A, Siefman D, Girardin G, Hursin M, Pautz A
PARCS few-group homogenized parameters generation using Serpent Monte Carlo code at the CROCUS reactor
In: 16h meeting of the international group on research reactors. sine loco: IGORR; 2014:(11 pp.). https://www.igorr.com/Documents/2014-BARILOCHE/AdolfoRAIS-CROCUS.pdf.
DORA PSI
Rydl A, Jaeckel B, Birchley JC, Lind T
Long-term SBO with selected mitigative measures: MELCOR parametric calculations for a 2-loop PWR
In: Proceedings of the 2014 22nd international conference on nuclear engineering (ICONE22). New York: American Society of Mechanical Engineers (ASME); 2014:V006T15A012 (10 pp.). https://doi.org/10.1115/ICONE22-30351
DORA PSI
Vasiliev A, Wieselquist W, Ferroukhi H, Canepa S, Heldt J, Ledergerber G
Validation studies of computational scheme for high-fidelity fluence estimations of the Swiss BWRs
In: Vol. 4. Progress in nuclear science and technology. Tokyo: Atomic Energy Society of Japan; 2014:99-103. https://doi.org/10.15669/pnst.4.99
DORA PSI
Wicaksono D, Zerkak O, Pautz A
Exploring variability in reflood simulation results: an application of functional data analysis
Presented at: 10th international topical meeting on nuclear thermal-hydraulics, operation and safety (NUTHOS-10); December 14-18, 2014; Okinawa, Japan.
DORA PSI
Wicaksono D, Zerkak O, Pautz A
Sensitivity analysis of a bottom reflood simulation using the Morris screening method
Presented at: 10th international topical meeting on nuclear thermal-hydraulics, operation and safety (NUTHOS-10); December 14-18, 2014; Okinawa, Japan.
DORA PSI
Wicaksono D, Grimm P, Vasiliev A, Hursin M, Perret G, Ferroukhi H
Validation of two Monte Carlo codes for LWR burnup calculations
Presented at: International conference on physics of reactors (PHYSOR 2014); September 28-October 3, 2014; Kyoto, Japan.
DORA PSI
Yang J, Suckow D, Prasser H-M, Michel F, Lind T
Assessment of RELAP5/TRACE against VEFITA thermal-hydraulic level swell tests
In: Proceedings of ICAPP 2014. Vol. 3. International congress on advances in nuclear power plants, ICAPP 2014. La Grange Park: American Nuclear Society; 2014:14154 (8 pp.).
DORA PSI
Yun Y, Leray O, Ferroukhi H
Uncertainty and sensitivity analysis of OECD/NEA UAM fuel thermal behaviour benchmark using a Falcon/URANIE methodology
Presented at: International conference on physics of reactors (PHYSOR 2014); September 28-October 3, 2014; Kyoto, Japan.
DORA PSI
Zanetti M, Luzzi L, Cammi A, Fiorina C
An innovative approach to dynamics modeling and simulation of the Molten Salt Rector Experiment
Presented at: International conference on physics of reactors (PHYSOR 2014); September 28-October 3, 2014; Kyoto, Japan.
DORA PSI
Andreani M, Zboray R
Simulation of the interaction of a horizontal jet with a stratified and condensing ambient in a large-scale, multi-compartment geometry
Presented at: 15th international topical meeting on nuclear reactor thermal - hydraulics, NURETH-15; May 12-15, 2013; Pisa, Italy.
DORA PSI
Bortot S, Wallenius J, Suvdantsetseg E, Pelloni S
Modeling issues in small HLMC fast reactors: ELECTRA case study
In: Vol. 109. Transactions of the American nuclear society. American Nuclear Society; 2013:2261-2264.
DORA PSI
Bubelis E, Schikorr M, Mansani L, Bandini G, Mikityuk K, Zhang Y, et al.
Safety analysis results of the DBC transients performed for the ALFRED reactor
In: Track 3 - safety. Vienna: International Atomic Energy Agency; 2013:IAEA-CN-199/298 (10 pp.).
DORA PSI
Canepa S, Hursin M, Ferroukhi H, Pautz A
Convergence studies of deterministic methods for LWR explicit reflector methodology
In: International conference on mathematics and computational methods applied to nuclear science and engineering (M&C 2013). Vol. 4. La Grange Park: American Nuclear Society; 2013:2868-2876. https://www.ans.org/store/item-700377/.
DORA PSI
Canepa S, Hursin M, Ferroukhi H, Pautz A
Preparation of nuclear libraries with deterministic and stochastic methods for LWR reflectors
In: International conference on mathematics and computational methods applied to nuclear science and engineering (M&C 2013). Vol. 4. La Grange Park: American Nuclear Society; 2013:2924-2934. https://www.ans.org/store/item-700377/.
DORA PSI
Dehbi A, Lind T, Suckow D, Guentay S
PSI steam generator project: mixing and recirculation
In: Proceedings of ICAPP 2013. International congress on advances in nuclear power plants, ICAPP 2013: nuclear power - a safe and sustainable choice for green future, held with the 28th KAIF/KNS annual conference. Daejeon: Korean Nuclear Society; 2013:FA123 (8 pp.).
DORA PSI
Fiorina C, Cammi A, Ricotti ME, Krepel J, Mikityuk K
Analysis of void reactivity and Doppler coefficient for thorium- and uranium-fuelled lead fast reactors
In: Proceedings of ICAPP 2013. Daejeon: Korean Nuclear Society; 2013:FD127 (10 pp.).
DORA PSI
Fiorina C, Krepel J
MSFR TRU-burining potential and comparison with an SFR
Presented at: GLOBAL 2013: International Nuclear Fuel Cycle Conference; September 29 - October 3, 2013; Salt Lake City, USA.
DORA PSI
Fiorina C, Franceschini F, Cammi A, Krepel J
The MSFR as a flexible CR reactor: the viewpoint of safety
In: Proceedings of GLOBAL 2013: international nuclear fuel cycle conference - nuclear energy at a crossroads. Vol. 2. La Grange Park, IL, USA: American Nuclear Society; 2013:833-842.
DORA PSI
Freixa J, Belaid S, Zerkak O
Thermal-hydraulic system code performance for SBLOCA phenomonelogy using different geometries and scales
Presented at: 15th international topical meeting on nuclear reactor thermal-hydraulics, NURETH-15; May 12-17, 2013; Pisa.
DORA PSI
Hursin M, Vasiliev A, Ferroukhi H, Pautz A
Comparison of SERPENT and CASMO-5M for pressurized water reactors models
In: International conference on mathematics and computational methods applied to nuclear science and engineering (M&C 2013). Vol. 3. La Grange Park, IL, USA: American Nuclear Society; 2013:1565-1576. https://www.ans.org/store/item-700377/.
DORA PSI
Khvostov G, Pautz A, Kolstad E, Ledergerber G
Analysis of a Halden LOCA test with the BWR high burnup fuel
In: LWR fuel performance meeting. TopFuel 2013. LaGrange Park, IL, USA: American Nuclear Society (ANS); 2013:644-651.
DORA PSI
Krepel J, Fiorina C, Kliem S
Advantages and dynamics features of liquid fueled MSR
In: Proceedings of the conference on molten salts in nuclear technology. sine loco: sine nomine; 2013:16-25.
DORA PSI
Krepel J, Hombourger B, Mikityuk K
Dependence of the thorium closed fuel cycle parameters on the moderation level of the molten salt reactor
In: Proceedings of ICAPP 2013. Daejeon, South Korea: Korean Nuclear Society; 2013:483-492.
DORA PSI
Lind T, Güntay S, Dehbi A, Suckow D
The results of the ARTIST project - consequence analysis of a spontaneous SGTR
In: Proceedings of ICAPP 2013. International congress on advances in nuclear power plants, ICAPP 2013: nuclear power - a safe and sustainable choice for green future, held with the 28th KAIF/KNS annual conference. Korean Nuclear Society; 2013:FA121 (10 pp.).
DORA PSI
Nikitin K, Gudmundsson T, Canepa S, Zerkak O, Ferroukhi H, Pautz A
Post-analysis of a turbine trip test at a BWR/6 using the TRACE/S3K coupled code
Presented at: 15th international topical meeting on nuclear reactor thermal-hydraulics, NURETH-15; May 12-17, 2013; Pisa.
DORA PSI
Papini D, Zerkak O, Prasser H
Simulation of international standard problem ISP-42 phase B using in-house coupled code GOTHIC-TRACE
Presented at: 15th international topical meeting on nuclear reactor thermal hydraulics, NURETH-15; May 12-15, 2013; Pisa, Italy.
DORA PSI
Paranjape S, Kapulla R, Mignot G, Paladino D, Zboray R
Light water reactor hollow cone containment spray performance tests in the presence of light non-condensable gas
Presented at: 15th international topical meeting on nuclear reactor thermal - hydraulics, NURETH-15; May 12-15, 2013; Pisa, Italy.
DORA PSI
Pascal V, Prulhière G, Fontaine B, Devan K, Chellapandi P, Kriventsev V, et al.
Benchmark calculations on control rod withdrawal tests performed during PHENIX end-of-life experiments
In: Proceedings of ICAPP 2013. Daejeon: Korean Nuclear Society; 2013:408-418.
DORA PSI
Perret G, Pattupara RM, Girardin G, Chawla R
Reanalysis of the gas-cooled fast reactor experiments at the zero power facility Proteus – spectral indices
In: Serot O, De Saint Jean C, Litaize O, Noguere G, eds. WONDER-2012 – 3rd international workshop on nuclear data evaluation for reactor applications. Vol. 42. EPJ web of conferences. sine loco: EDP Sciences; 2013:05002 (5 pp.). https://doi.org/10.1051/epjconf/20134205002
DORA PSI
Wallenius J, Bortot S, Suvdantsetseg E
Electra-forte, A really small SMR for the Canadian market
In: Vol. 109. Transactions of the American nuclear society. American Nuclear Society; 2013:2258-2260.
DORA PSI
Wicaksono D, Zerkak O, Nikitin K, Ferroukhi H, Chawla R
Application of power time-projection on the operator-splitting coupling scheme of the trace/S3K coupled code
In: International conference on mathematics and computational methods applied to nuclear science and engineering (M&C 2013). Vol. 3. La Grange Park, IL, USA: American Nuclear Society; 2013:1748-1760. https://www.ans.org/store/item-700377/.
DORA PSI
Zboray R, Mignot G, Paladino D
Erosion and break-up of light-gas layers by horizontal injections in containment relevant atmosphere
Presented at: 15th international topical meeting on nuclear reactor thermal - hydraulics, NURETH-15; May 12-15, 2013; Pisa, Italy.
DORA PSI
Zboray R, Prasser H, Stark M
Examining annular flows in a tight-lattice fuel bundle model by cold-neutron imaging
Presented at: 15th international topical meeting on nuclear reactor thermal hydraulics, NURETH-15; May 12-15, 2013; Pisa, Italy.
DORA PSI
Chawla R, Rätz D, Jordan KA, Perret G
Analysis of pin removal experiments conducted in an SCWR-like test lattice
In: PHYSOR 2012: advances in reactor physics. Vol. 4. La Grange Park, IL, USA: American Nuclear Society; 2012:3565-3578. https://www.ans.org/store/item-700371/.
DORA PSI
Dokhane A, Canepa S, Ferroukhi H
Transition to CASMO-5M and SIMULATE-3K for Stability Analyses of the Swiss BWRs
Presented at: PHYSOR 2012: advances in reactor physics - linking research, industry, and education.
DORA PSI
Fernandez-Moguel L
Preliminary analysis of air ingress experiment QUENCH-16 using RELAP/SCDAPSim3.5 and MELCOR 1.8.6
Presented at: 21st international conference nuclear energy for New Europe; September 5-7, 2012; Ljubljana.
DORA PSI
Ferroukhi H, Vasiliev A, Dufresne A, Chawla R
Towards a reference numerical scheme using MCNPX for PWR control rod tip fluence estimations
In: PHYSOR 2012: advances in reactor physics. Vol. 1. La Grange Park, IL, USA: American Nuclear Society; 2012:401-417. https://www.ans.org/store/item-700371/.
DORA PSI
Grimm P, Perret G
Experimental validation of CASMO-4E and CASMO-5M for radial fission rate distributions in a westinghouse SVEA-96 Optima2 BWR fuel assembly
In: PHYSOR 2012: advances in reactor physics. Vol. 4. La Grange Park, IL, USA: American Nuclear Society; 2012:3410-3421. https://www.ans.org/store/item-700371/.
DORA PSI
Grimm P, Vasiliev A, Wieselquist W, Ferroukhi H, Ledergerber G
Reactor physics studies for assessment of tramp uranium methods
In: Advances in reactor physics. Vol. 2. LaGrange Park, IL, USA: American Nuclear Society; 2012:1522-1535.
DORA PSI
Hursin M, Perret G
Design of a PROTEUS lattice representative of a burnt and fresh fuel interface at power conditions in light water reactors
In: PHYSOR 2012: advances in reactor physics. Vol. 5. La Grange Park: American Nuclear Society; 2012:(12 pp.).
DORA PSI
Hursin M, Koeberl O, Perret G
Towards the reanalysis of void coefficients measurements at PROTEUS for High Conversion Light Water Reactor lattices
In: PHYSOR 2012: advances in reactor physics. Vol. 3. La Grange Park, IL, USA: American Nuclear Society; 2012:2558-2568. https://www.ans.org/store/item-700371/.
DORA PSI
Karanki DR, Dang VN, Kim T-W
The impact of dynamics on the MLOCA accident model - an application of dynamic event trees
In: 11th international probabilistic safety assessment and management conference and the annual european safety and reliability conference 2012. (PSAM11 ESREL 2012). Vol. 3. sine loco: IAPSAM; ESRA; 2012:2468-2479. https://www.iapsam.org/www.psam11.org/www/fi/index.php.html.
DORA PSI
Krack M
Atomistic simulation of nuclear fuels
In: Vol. 1383. Materials research society symposium proceedings. ; 2012:19-25. https://doi.org/10.1557/opl.2012.520
DORA PSI
Pelloni S, Mikityuk K
Nuclear data uncertainty analysis for the generation IV gas-cooled fast reactor
In: PHYSOR 2012: advances in reactor physics. Vol. 3. La Grange Park, IL, USA: American Nuclear Society; 2012:2592-2604. https://www.ans.org/store/item-700371/.
DORA PSI
Sun K, Chenu A, Mikityuk K, Krepel J, Chawla R
Coupled 3D-neutronics / thermal-hydraulics analysis of an unprotected loss-of-flow accident for a 3600 MWth SFR core
In: PHYSOR 2012: advances in reactor physics. Vol. 4. La Grange Park, IL, USA: American Nuclear Society; 2012:3231-3245. https://www.ans.org/store/item-700371/.
DORA PSI
Wieselquist W, Vasiliev A, Ferroukhi H
Nuclear data uncertainty propagation in a lattice physics code using stochastic sampling
In: PHYSOR 2012: advances in reactor physics. Vol. 4. La Grange Park, IL, USA: American Nuclear Society; 2012:3000-3015. https://www.ans.org/store/item-700371/.
DORA PSI
Zhu T, Vasiliev A, Wieselquist W, Ferroukhi H
Stochastic sampling method with MCNPX for nuclear data uncertainty propagation in criticality safety applications
In: PHYSOR 2012: advances in reactor physics. Vol. 1. La Grange Park, IL, USA: American Nuclear Society; 2012:144-157. https://www.ans.org/store/item-700371/.
DORA PSI
Karanki DR, Dang VN, Kim T-W
Discrete dynamic event tree analysis of MLOCA using ADS-TRACE
In: International topical meeting on probabilistic safety assessment and analysis (PSA 2011). Vol. 1. La Grange Park, IL, USA: American Nuclear Society; 2011:610-622. https://www.ans.org/store/item-700366/.
DORA PSI
Khvostov G, Wiesenack W, Oberländer BC, Kolstad E, Ledergerber G, Zimmermann MA
Post-test analysis of the Halden LOCA experiment IFA-650.7 using the Falcon code
In: Proceedings of the enlarged Halden project group meeting, EHPG 2011. Halden, Norway: sine nomine; 2011:F2.2 (10 pp.).
DORA PSI
Khvostov G, Kolstad E, Ledergerber G, Zimmermann MA, Wiesenack W, Brémond O, et al.
Pre-calculation using the Falcon fuel behaviour code of the fuel rod design parameters and the test-conditions for a two-run Halden LOCA test with KKL BWR high-burnup fuel
In: Enlarged Halden programme group meeting. Proceedings of the fuel & materials sessions. Vol. HPR-374. Halden, Norway: Institutt for Energiteknikk; 2011:F2.7 (21 pp.).
DORA PSI
Khvostov G, Zimmermann MA, Lyon W, Pytel M
Towards advanced modeling of MPS-assisted cladding failure during power ramps using the FALCON code
Presented at: 2011 Water reactor fuel performance meeting/LWR/Top fuel; September 11-14, 2011; Chengdu, China.
DORA PSI
Perret G, Jordan KA
On the combination of delayed neutron and delayed gamma techniques for fission rate measurement in nuclear fuel
In: ANIMMA 2011. Proceedings. 2nd international conference on advancements in nuclear instrumentation, measurement methods and their applications. International conference on advancements in nuclear Instrumentation measurement methods and their applications (ANIMMA). Piscataway: IEEE; 2011:(7 pp.). https://doi.org/10.1109/ANIMMA.2011.6172907
DORA PSI
Yancey K, Mikityuk K, Krepel J, Chenu A
Development and application of a comprehensive model of a lead-cooled fast reactor using the FAST code system
In: Winter meeting 2011. Vol. 105. Transactions of the American Nuclear Society. La Grange Park: American Nuclear Society; 2011:699-700. https://www.ans.org/pubs/transactions/article-13076/.
DORA PSI
Yun Y, Khvostov G, Freixa J, Zimmermann MA
Analysis of fuel rod behaviour in a EPR^TM during the base irradiation and LOCA-transient utilizing the FALCON code
In: Proceedings of the 2010 LWR fuel performance/top fuel/WRFPM. sine loco: American Nuclear Society; 2011:345-353.
DORA PSI
Zboray R, Guetg M, Kickhofel J, Prasser H-M
Investigating annular flows and the effect of functional spacers in an adiabatic double-subchannel model of a BWR fuel bundle by ultra-fast X-ray Tomography
Presented at: 14th international topical meeting on nuclear reactor thermalhydraulics, NURETH-14; September 25-30, 2011; Toronto, Ontario, Canada.
DORA PSI
Zimmermann MA, Dang VN, Lanore J-M, Probst P, Hortal J, Amri A
Insights from the SM2A pilot study towards quantification of a change of plant safety margin after a hypothetical power up-rate
In: International topical meeting on probabilistic safety assessment and analysis (PSA 2011). Vol. 3. La Grange Park, IL, USA: American Nuclear Society; 2011:2281-2294. https://www.ans.org/store/item-700366/.
DORA PSI
Bertolotto D, Manera A, Petrov V, Bissels WM, Prasser HM, Chawla R
Set-up of a validation strategy for the coupled code CFX/TRACE in the FLORIS facility with the aid of CFD simulations
In: Proceedings of ICAPP '10. Vol. 2. International congress on advances in nuclear power plants 2010, ICAPP 2010. La Grange Park: American Nuclear Society; 2010:1529-1537.
DORA PSI
Chanaron B, Ahnert C, Bestion D, Zimmermann M, Cacuci D, Crouzet N
The European project NURISP for nuclear reactor simulation
In: Proceedings of the 2010 ANS annual meeting and embedded topical meeting: isotopes for medicine and industry. Vol. 103. Transactions of the American nuclear society. sine loco: sine nomine; 2010:671-672.
DORA PSI
Chawla R, Girardin G, Joneja OP
Reactor experiments course of the Swiss Nuclear Engineering master
In: Proceedings of the 18th international conference on nuclear engineering, ICONE18. Vol. 2. International conference on nuclear engineering, proceedings, ICONE. New York: American Society of Mechanical Engineers; 2010:323-330. https://doi.org/10.1115/ICONE18-29183
DORA PSI
Chawla R, Ansermet JP, Cavedon JM, Hirt P, Kröger W, Prasser HM, et al.
The Swiss master in nuclear engineering: a collaboration between universities, research centre and industry
In: 18th international conference on nuclear engineering. Vol. 2. international conference on nuclear engineering, proceedings, ICONE. New York City: American Society of Mechanical Engineers; 2010. https://doi.org/10.1115/ICONE18-29218
DORA PSI
Chenu A, Mikityuk K, Chawla R
A coupled 3D neutron kinetics/thermal-hydraulics model of the generation IV sodium-cooled fast reactor
In: Proceedings of ICAPP '10. Vol. 2. International congress on advances in nuclear power plants 2010, ICAPP 2010. sine loco: sine nomine; 2010:1331-1337.
DORA PSI
Chenu A, Mikityuk K, Chawla R
Modeling of friction pressure drop for sodium two-phase flow in round tubes
In: Proceedings of ICAPP '10. Vol. 3. International congress on advances in nuclear power plants 2010, ICAPP 2010. sine loco: sine nomine; 2010:1637-1644.
DORA PSI
Dang VN, Kim T-W, Zimmermann MA, Manera A
Assessing safety margins: the impact of a power uprate on risk from small and medium LOCA scenarios
In: 10th international conference on probabilistic safety assessment & management, PSAM10. Vol. 1. sine loco: IAPSAM; ESRA; 2010:83-92. https://www.iapsam.org/psam10/index.html.
DORA PSI
Ferroukhi H, Hofer K
Coupled 3-D neutronics/thermal-hydraulic core analysis of a BWR nuclear heating transient
In: Proceedings of the international conference on the physics of reactors 2010 (PHYSOR 2010). Vol. 3. International conference on the physics of reactors 2010, PHYSOR 2010. La Grange Park: American Nuclear Society; 2010:2422-2436.
DORA PSI
Giust FD, Grimm P, Chawla R
Experimental comparisons of 3D reconstructed pin-power distributions in full-scale BWR fuel assemblies
In: Proceedings of the 18th international conference on nuclear engineering, ICONE18. Vol. 2. International conference on nuclear engineering, proceedings, ICONE. New York: American Society of Mechanical Engineers; 2010:ICONE18-29691 (10 pp.). https://doi.org/10.1115/ICONE18-29691
DORA PSI
Ivanova T, Fernex F, Kolbe E, Vasiliev A, Lee GS, Woo SW, et al.
OECD/NEA expert group on uncertainty analysis for criticality safety assessment: current activities
In: Advances in reactor physics to power the nuclear renaissance. Vol. 3. International conference on the physics of reactors 2010, PHYSOR 2010. La Grange Park: American Nuclear Society; 2010:2212-2226.
DORA PSI
Khvostov G, Zimmermann MA, Ledergerber G
Parametric study of fuel rod behaviour during the RIA using the modified FALCON code
In: Nuclear fuel behaviour during reactivity initiated accidents. Workshop proceedings. sine loco: OECD; 2010:247-258.
DORA PSI
Nikitin K, Judd J, Grandi GM, Manera A, Ferroukhi H
Peach bottom 2 turbine trip 2 simulation by TRACE/S3K coupled code
In: International conference on the physics of reactors 2010. Vol. 3. International conference on the physics of reactors 2010, PHYSOR 2010. La Grange Park: American Nuclear Society; 2010:2283-2293.
DORA PSI
Petrov V, Manera A
Development and validation of a CFD model for the EPR™ pressure vessel
In: Proceedings of ICAPP '10. Vol. 3. International congress on advances in nuclear power plants 2010, ICAPP 2010. La Grange Park: American Nuclear Society; 2010:1685-1691.
DORA PSI
Rineiski A, Rimpault G, Glinatsis G, Messaoudi N, Pelloni S, Schwenk-Ferrero A, et al.
Decay heat benchmark for uranium-free fuels with Minor Actinides
In: Proceedings of the 18th international conference on nuclear engineering, ICONE18. Vol. 2. International conference on nuclear engineering, proceedings, ICONE. New York: American Society of Mechanical Engineers; 2010:ICONE18-29654 (10 pp.). https://doi.org/10.1115/ICONE18-29654
DORA PSI
Sun K, Krepel J, Mikityuk K, Chawla R
Void reactivity decomposition for the sodium-cooled fast reactor in equilibrium closed fuel cycle
In: Proceedings of the international conference on the physics of reactors 2010 (PHYSOR 2010). Vol. 3. International conference on the physics of reactors 2010, PHYSOR 2010. La Grange Park: American Nuclear Society; 2010:1779-1790.
DORA PSI
Vasiliev A, Pittarello R, Ferroukhi H, Kolbe E
Verification of PWR in- and ex- vessel neutron fluence calculations with MCNPX, based on the "H.B. Robinson-2" dosimetry benchmark
In: Proceedings of the international conference on the physics of reactors. Vol. 1. International conference on the physics of reactors 2010, PHYSOR 2010. La Grange Park: American Nuclear Society; 2010:838-847.
DORA PSI

Simulations And Measurements Of Adiabatic Annular Flows In A Triangular, Tigth Lattice Nuclear Fuel Bundle Model
A Saxena, R Zboray, H Prasser
Cfd4nrs-5: Proceedings Of The Oecd/Nea & Iaea Workshop On Computational Fluid Dynamics For Nuclear Safety Research, Eth Zuerich, Switzerland, Sep. 9-11, 2014 1, 10 (2014)

NUSS-RF: Stochastic Sampling-Based Tool For Nuclear Data Sensitivity And Uncertainty Quantification
T. Zhu, A. Vasiliev, H. Ferroukhi, A. Pautz
Proc. Int. Conf. Reactor Physics, Physor2014, Kyoto, Japan, September 28 - October 3, 2014

Stochastic Sampling-Based Tool For Nuclear Data Sensitivity Uncertainty Quantification
T. Zhu, A. Vasiliev, H. Ferroukhi, A. Pautz
Proc. Int. Youth. Nucl. Congress Iync2014, Burgos, Spain, July 6-12, 2014

Analysis Of Axial Fuel Relocation Based On Gamma Scan Data From Oecd Halden Reactor Project Loca Tests
V. Brankov, G. Khvostov, K. Mikityuk, A.Pautz
Proc. Water Reactor Fuel Performance Meeting Wrfpm2014, Sendai, Japan, September 14-17, 2014

Fuel Relocation In IFA-650 Loca Tests Based On Gamma Scan Data
V. Brankov, G. Khvostov, K. Mikityuk, A.Pautz
Proc. Enlarged Halden Project Group Meeting, Roeso, Norway, September 7-12, 2014

The hydrodynamics of two-phase flow in a tube bundle and a bare channel
T.T. Betschart, D.J. Suckow, V. Brankov, H.-M. Prasser
ICAPP, Charlotte, USA

Remaining Issues in Pool Scrubbing: Major Drivers for Experimentation within the EU-PASSAM Project
L.E. Herranz, R.D. Tardáguila, T.T. Berschart, T.M. Lind, S. Morandi
ICAPP, Charlotte, USA

Assessment of RELAP5/TRACE against VEFITA Thermal-Hydraulic Level Swell Tests
J. Yang, D.J. Suckow, H.-M. Prasser, M. Furrer, T.M. Lind
ICAPP, Charlotte, USA

Investigation Of The Influence Of Off-Stoichiometry On The Radiation Damage Evolution In Uranium Dioxide
R. Ngayam-Happy, M. Krack
Proc. European Material Research Socitey Meeting E-Mrs 2013, Strasbourg, France, May 27-31, 2013

Simulation Of International Standard Problem ISP-42 Phase B Using The Containment Code GOTHIC
D. Papini, C. Adamsson, M. Andreani And H.M. Prasser
Proc. Nuclear Reactor Thermal-Hydraulics Nureth-15, Pisa, Italy, May 12-17, 2013

On BWR Regional Oscillations With Rotational Symmetry Line Using Simulate-3K
A. Dokhane, H. Ferroukhi, A. Pautz
Proc. Mathematics And Computations M&C 2013, Sun Valley, Usa, May 5-9, 2013

Preparation Of Nuclear Libraries With Deterministic And Stochastic Methods For LWR Reflectors
S. Canepa, M. Hursin, H. Ferroukhi, A. Pautz
Proc. Mathematics And Computations M&C 2013, Sun Valley, Usa, May 5-9, 2013

Convergence Studies Of Deterministic Methods For LWR Explicit Reflector Methodology
S. Canepa, M. Hursin, H. Ferroukhi, A. Pautz
Proc. Mathematics And Computations M&C 2013, Sun Valley, Usa, May 5-9, 2013

Comparison Of U.S Nrc Parcs Against Studsvik Simulate-3 Core Simulator For Modeling And Analysis Of Swiss Pwrs
S. Bogetic, M. Hursin, A. Dokhane, H. Ferroukhi, S. Canepa, A. Pautz
Proc. America Nuclear Society 2013 Student Conference, Mit, Boston, April 4-6, 2013

Study Of Nuclear Decay Data Contribution To Uncertainties In Heat Load Estimations For Spent Fuel Pools
H. Ferroukhi, O. Leray, M. Hursin, A. Vasiliev, G. Perret, A. Pautz
Proc. Nuclear Data Conference Nd2013, New York City, Usa, March 4-8, 2013

Nuclear Data Library E Ects On Fast To Thermal Flux Shapes Around Pwr Control Rod Tips
A. Vasiliev, H. Ferroukhi, T. Zhu, A. Pautz
Proc. Nuclear Data Conference Nd2013, New York City, Usa, March 4-8, 2013

Application Of The Psi-Nuss Tool For The Estimation Of Nuclear Data Related K-Eff Uncertainties For The Oecd/Nea Wpncs Uacsa Phase I Benchmark
T. Zhu, A. Vasiliev, H. Ferroukhi, A. Pautz
Proc. Nuclear Data Conference Nd2013, New York City, Usa, March 4-8, 2013

Comparison Of Two Approaches For Nuclear Data Uncertainty Propagation In Mcnp(X) For Selected Fast Spectrum Critical Benchmarks
T. Zhu, D. Rochman, A. Vasiliev, H. Ferroukhi, W. Wieselquist, A. Pautz
Proc. Nuclear Data Conference Nd2013, New York City, Usa, March 4-8, 2013

Multi-Scale Approach To Advanced Fuel Modelling For Enhanced Safety
F. Ribeiro, G. Khvostov
Proc. Eurosafe Meeting, Cologne, Germany, November 4-5, 2013 <

Deposition Of Inertial Drops In Eulerian Formulation
D. Caraghiaur, C. Adamsson, H. Anglart
Proc. Nureth-15, Pisa, Italy, May 12-17, 2013

The results of the ARTIST project - consequence analysis of a spontaneous SGTR
T.M. Lind, S. Güntay, A. Dehbi, D.J. Suckow
ICAPP, Jeju Island, South Korea

PSI Steam Generator Project: Mixing and Recirculation
A. Dehbi, T.M. Lind, D.J. Suckow, S. Güntay
ICAPP, Jeju Island, South Korea

Status of the Spent Fuel in the reactor buildings of Fukushima Daiichi 1-4
B.S. Jäckel
22^nd NENE Conference, Bled, Slovenia
http://www.nss.si/proc/nene2013/pdf/NENE2013_1203.pdf

High resolution two-phase flow structure investigations in tube bundles
T.T. Betschart, D.J. Suckow, H.-M. Prasser, S. Güntay
15^th NURETH Conference, Pisa, Italy

Flow and Heat Transfer in a Particle Laden Differentially Heated Cavity
J. Kalilainen, P. Rantanen, T.M. Lind, A. Dehbi, A. Auvinen
15^th NURETH Conference, Pisa, Italy

Pre-Test CFD Simulations of the Effect of Leakage on Mixing in a Steam Generator Mock-up
A. Dehbi, T.L. Chiu
15^th NURETH Conference, Pisa, Italy

2D RANS and LES Simulations of Turbulent Flow inside a Differentially Heated Cavity
A. Dehbi, M. Aksouh, J. Kalilainen
15^th NURETH Conference, Pisa, Italy

The EURATOM-ROSATOM ERCOSAM-SAMARA Projects on Containment Thermal-hydraulics of current and future LWRs for Severe Accident Management
D. Paladino, S. Güntay, M. Andreani, I. Tkatschenko, J. Brinster, F. Dabbene, S. Kelm, H.-J. Allelein, D.C. Visser, S. Benz, T. Jordan, Z. Liang, E. Porcheron, J. Malet, A. Bentaib, A. Kiselev, T. Yudina, A. Filippov, A. Khizbullin, M. Kamnev, A. Zaytsev, A. Loukianov
ICAPP, Chicago, USA

Simulation Of International Standard Problem Isp-42, Phases A And B With The TRACE Code
C. Adamsson, D. Papini, O.Zerkak, H.M. Prasser
Proc. Int. Top.Mtg. Nuclear Thermal-Hydraulics, Operatio And Safety, Nuthos-9, Kaohsiung, China, September 9-13, 2012

Study Of Condensation Heat Transfer In Passive Safety Systems Using GOTHIC And TRACE Codes
D. Papini, C. Adamsson, M. Andreani, H.M. Prasser
Proc. Int. Top.Mtg. Nuclear Thermal-Hydraulics, Operatio And Safety, Nuthos-9, Kaohsiung, China, September 9-13, 2012

Simulation Of Complex Transient Flow Patterns In The ESBWR Passive Containment Cooling System
C. Adamsson, D. Papini, O.Zerkak, H.M. Prasser
Proc. Int. Top.Mtg. Nuclear Thermal-Hydraulics, Operatio And Safety, Nuthos-9, Kaohsiung, China, September 9-13, 2012

Performance Of Heat Transfer Models Of Thermal-Hydraulic System Codes At The Invert Edwards Pipe Experiment
R. Szijarto, J. Freixa, H.M. Prasser
Proc. Int. Top.Mtg. Nuclear Thermal-Hydraulics, Operatio And Safety, Nuthos-9, Kaohsiung, China, September 9-13, 2012

Validation Studies Of Computational Scheme For High-Fidelity Fluence Estimations Of The Swiss BWRs
A. Vasiliev, W. Wieselquist, H. Ferroukhi, S. Canepa, J. Heldt, G. Ledergerber
Proc. Int. Conf. On Radiation Protection And Shielding, Rpsd/Icrs-12, Nara, Japan, September 2-7, 2012

Evaluation Of The Fuel Rod Behaviour In A BWR Spent Fuel Pool Under Boil-Off Conditions
H. Ferroukhi, G. Khvostov, O. Zerkak, A. Vasiliev, M.A. Zimmermann
Proc. Int. Workshop On Nuclear Safety And Severe Accidents, Nussa, Peking, China, September 7-8, 2012

Validation Of Kenorest With LWR-Proteus Phase Ii Samples
M. Wagner, R. Kilger, A. Pautz, W. Zwermann, P.Grimm, A. Vasiliev, H. Ferroukhi
Proc. Jahrestagung Kerntechnik, May 22-24, 2012, Stuttgart, Germany, 2012

Validation of a CFD Model for Steam Condensation in the Presence of Noncondensable Gases
A. Dehbi, F. Janasz, B. Bell
4^th CFD4NRS, Daejeon, South Korea

Conduct and Analytical Support to Air Ingress Experiment QUENCH-16
J.C. Birchley, L. Fernandez-Moguel, C. Bals, E. Beuzet, Z. Hozer, J. Stuckert
5^th ERMSAR, Cologne, Germany

Progress in SARNET2 WP5-2 Research: Melt Pool Behavior and Coolability in the Lower Head of a Light Water Reactor
W.M. Ma, W. Villanueva, P. Kudinov, A. Miassoedov, X. Gaus-Liu, M. Hoffmann, B.S. Jäckel, J.C. Birchley, P. Matejovic, M. Barnak
5^th ERMSAR, Cologne, Germany

Large Scale Experimental Program at PSI on Safety Issues in a PWR Steam Generator
A. Dehbi, D.J. Suckow, T.M. Lind, S. Güntay
5^th ERMSAR, Cologne, Germany

CFD Study of Natural Convection Mixing in a Steam Generator Mock-up: Comparison between Full Geometry and Porous Media Approaches
A. Dehbi, H. Badreddine
ICAPP, Chicago, USA

Granular flow in pebble bed reactors: dust generation and scaling
C.H. Rycroft, T.M. Lind, S. Güntay, A. Dehbi
ICAPP, Chicago, USA

Effects of molybdenum and silver on iodine transport in primary circuit on severe nuclear accidents
J. Kalilainen, P. Rantanen, T. Kärkelä, M. Lipponen, A. Auvinen, J. Jokiniemi
ICAPP, Chicago, USA

Corium and Debris Coolability Studies Performed in the Severe Accident Research Network of Excellence (SARNET2)
A. Miassoedov, T.W. Tromm, J.C. Birchley, F. Fichot, W.M. Ma, G. Pohlner, P. Matejovic
20^th ICONE Conference, Anaheim, USA
http://dx.doi.org/10.1115/ICONE20-POWER2012-54568

Progress with Iodine Chemistry Studies in SARNET2
T.J. Haste, A. Auvinen, L. Cantrel, J. Kalilainen, T. Kärkelä, B. Simondi-Teisseire
21^st NENE Conference, Ljubljana, Slovenia
http://www.nss.si/proc/nene2012/Publication_datoteke/Proceedings/501.pdf

Oecd/Nea Main Steam Line Break PWR Benchmark Simulation By TRACE/S3k Coupled Code
K. Nikitin, A. Manera, H. Ferroukhi, J. Judd, G.M. Grandi
Proc. Int. Top.Meetg. Nuclear Reactor Thermalhydraulics, Nureth-14, Toronto, Canada, September 25-30, 2011

Post-Test Thermal-Hydraulic Analysis Of Two Intermediate Loca Tests At The Rosa Facility Including Uncertainty Evaluation
J. Freixa, T-W. Kim, A. Manera
Proc. Int. Top.Meetg. Nuclear Reactor Thermalhydraulics, Nureth-14, Toronto, Canada, September 25-30, 2011

Testing Of The Quicktest-Ultimate Algorithm To Solve The Dissolved Convection Equation During A Boron Dilution Test At The PKL Facility
J. Freixa, T-W. Kim, A. Manera
Proc. Int. Top.Meetg. Nuclear Reactor Thermalhydraulics, Nureth-14, Toronto, Canada, September 25-30, 2011

Validation Of Star-Ccm+ For Bouyancy Driven Mixing In A PWR Reactor Pressure Vessel
V. Petrov, A. Manera
Proc. Int. Top.Meetg. Nuclear Reactor Thermalhydraulics, Nureth-14, Toronto, Canada, September 25-30, 2011

Analysis Of The Performance Of The Kerena Emergency Condenser
A. Manera, H.M. Prasser, S. Leyer
Proc. Int. Top.Meetg. Nuclear Reactor Thermalhydraulics, Nureth-14, Toronto, Canada, September 25-30, 2011

Prediction Of Void Fraction In A Subchannel And Bundle Geometry With FLICA4 And TRACE
T-W. Kim, A. Manera
Proc. Int. Top.Meetg. Nuclear Reactor Thermalhydraulics, Nureth-14, Toronto, Canada, September 25-30, 2011

Revisiting Temporal Accuracy In Neutronics/T-H Code Coupling Using The Nuresim LWR Simulation Platform
O. Zerkak, I. Gajev, A. Manera, T. Kozlowski, A. Gommlich, S. Zimmer, S. Kliem, N. Crouzet, M.A. Zimmermann
Proc. Int. Top.Meetg. Nuclear Reactor Thermalhydraulics, Nureth-14, Toronto, Canada, September 25-30, 2011

Post-Test Analysis Of The Halden Loca Experiment Ifa-650.7 Using The Falcon Code.
G. Khvostov, W. Wiesenack, B.C. Oberlander, E. Kolstad, G. Ledergerber, M.A. Zimmermann
Proc. Enlarged Halden Project Group Meeting, Sandefjord, Norway, October 2-7, 2011

Assessment Of Mcnpx/Cinder For Burnup Calculations
E. Kolbe, P. Grimm, A. Vasiliev, H. Ferroukhi
Proc. Int. Conf. On Nuclear Criticality Icnc 2011, Edinburgh, Scotland, September 19-22, 2011

Criticality Safety Evaluation Of A Swiss Wet Storage Pool Including Limited Buc And Uncertainty Analysis
E. Kolbe, P. Grimm, A. Vasiliev, H. Ferroukhi
Proc. Int. Conf. On Nuclear Criticality Icnc 2011, Edinburgh, Scotland, September 19-22, 2011

Towards Advanced Modelling Of Mps-Assisted Cladding Failure During Power Ramps Using The Falcon Code
G. Khvostov, M.A. Zimmerman, W. Lyon, M. Pytel
Proc. Water Reactor Fuel Performance Meeting 2011, Chengdu, China, September 11-14, 2011

Development And Test Validation Of A Computational Scheme For High-Fidelity Fluence Estimations Of The Swiss BWRs
A. Vasiliev, W. Wieselquist, H. Ferroukhi, S. Canepa
Proc. Int. Conf. On Mathematics And Computational Methods Applied To Nucl. Science And Engineering,(M&C2011), Rio De Janeiro, Brazil, May 8-12, 2011

A Trend Analysis Methodology For Enhanced Validation Of 3-D LWR Core Simulations
W. Wieselquist, H. Ferroukhi, K. Bernatowicz
Proc. Int. Conf. On Mathematics And Computational Methods Applied To Nucl. Science And Engineering,(M&C2011), Rio De Janeiro, Brazil, May 8-12, 2011

Towards An Uncertainty Quantification Methodology With CASMO-5
W. Wieselquist, A. Vasiliev, H. Ferroukhi
Proc. Int. Conf. On Mathematics And Computational Methods Applied To Nucl. Science And Engineering,(M&C2011), Rio De Janeiro, Brazil, May 8-12, 2011

Development And Validation Of A Coupled CFD/System-Code Tool
D. Bertolotto, A. Manera, R. Chawla
Proc. Int. Congress On Advances in Nuclear Power Plants (Icapp2011), Nice, France, May 2-5, 2011

Presentation Of The Multi-Physics Subproject Of The Nurisp European Project
J. Jimenez,M.A. Zimmermann, O. Zerkak ,Ph. Emonot
Proc. Annual Meeting of The Spanish Nuclear Society 2011

Vipre-W/Mefisto-T - A Mechanistic Toll For Transient Predictions Of Dryout In BWR Fuel
C. Adamsson, J-M. Le Corre,
Proc. Nureth-14, Toronto, Canada, September 25-30, 2011

Transient Void, Pressure Drop And Critical Power BFBT Benchmark Analysis And Results With Vipre-W/Mefisto-T
J-M. Le Corre, C. Adamsson, P. Alvarez
Proc. Nureth-14, Toronto, Canada, September 25-30, 2011

On A Best-Estimate Approach To Calculation Of Dryout Probability During BWR Transients
C. Adamsson, J-M. Le Corre,
Proc. Nureth-14, Toronto, Canada, September 25-30, 2011

Discted Dynamic Event Tree Analysis Of Mloca Using ADS-TRACE
D.R. Karanki, V.N. Dang, T-W. Kim
Proc. Top. Meetg. On Probabilistic Safety Assessment And Analysis, Ans Psa2011, Wilimington, Us, March 13-17, 2011

Scaling of a PWR Steam Generator Simulator with the Help of CFDA
A. Dehbi, H. Badreddine
14^th NURETH Conference, Toronto, Canada

An Overview of past and present Activities in the Severe Accident Domain within the Framework of WGAMA
S. Güntay
14^th NURETH Conference, Toronto, Canada

Quantitative Analysis Of Effect Of Power Uprate On Core Damage Frequency Of Mbloca
T.W. Kim, V.N. Dang, M.A. Zimmermann, A. Manera
Proc. Int. Mtg. On Nucl. Thermal-Hydraulics, Operation And Safety Nuthos-8, Shanghai, China, October 10-14, 2010

Thermal-Hydraulic Analysis Of An Intermediate Loca Test At The Rosa Facility Including Uncertainty Evaluation
J. Freixa, T-W. Kim, A. Manera
Proc. Int. Mtg. On Nucl. Thermal-Hydraulics, Operation And Safety Nuthos-8, Shanghai, China, October 10-14, 2010

Development And Validation Of A CFD Model For The EPR Pressure Vessel
V. Petrov, A. Manera
Proc. Int. Congress On Advances in Nuclear Power Plants (Icapp'10), San Diego, California, Usa, June 13-17, 2010

Set-Up Of A Validation Strategy For The Coupled Code CFX/TRACE In The Floris Facility With The Aid Of CFD Simulations
D. Bertolloto,
Proc. Int. Congress On Advances in Nuclear Power Plants (Icapp'10), San Diego, California, Usa, June 13-17, 2010

Coupled 3-D Neutronics/Thermal-Hydraulic Core Analysis Of A BWR Nuclear Heating Transient
H. Ferroukhi, K. Hofer
Proc. Int. Conf. Advances in Reactor Physics To Power The Nuclear Renaissance, Physor 2010 Pittsburgh, Usa, May 9-14, 2010

Peach Bottom 2 Turbine Trip 2 Simulation By TRACE/S3k Coupled Code
K. Nikitin, J. Judd, G.M. Grandi, A. Manera, H. Ferroukhi
Proc. Int. Conf. Advances in Reactor Physics To Power The Nuclear Renaissance, Physor 2010 Pittsburgh, Usa, May 9-14, 2010

Verification Of PWR In- And Ex- Vessel Neutron Fluence Calculations With Mcnpx, Based On The H.B. Robinson-2 Dosimetry Benchmark
A. Vasiliev, R. Pittarello, H. Ferroukhi, E. Kolbe
Proc. Int. Conf. Advances in Reactor Physics To Power The Nuclear Renaissance, Physor 2010 Pittsburgh, Usa, May 9-14, 2010

Assessment Of The Jeff-3.1.1 Neutron Data Library For Cse Of LWR Fuel Storage Pools
E. Kolbe, A. Vasiliev, H. Ferroukhi
Proc. Int. Conf. On Nuclear Data For Science And Technology, Nd2010, Jeju Island, Korea, 26-30 April, 2010

Comparison Of Neutron Data Libraries For The Analysis Of The H.B.Robinson-2 Pressure Vessel Benchmark With The MCNPX Code
A. Vasiliev, R. Pittarello, E. Kolbe, H. Ferroukhi
Proc. Int. Conf. On Nuclear Data For Science And Technology, Nd2010, Jeju Island, Korea, 26-30 April, 2010

Some Insights Into The Role Of Axial Gas Flow In Fuel Rod Behaviour During The Loca Based On Hrp Experiments And Results Of Calculation By Falcon Coupled With The Frelax Model
G. Khvostov, M.A. Zimmermann, W. Wiesenack, G. Ledergerber
Proc. Enlarged Halden Group Meeting, Norway, 14-19 March 2010

Core-Shell Vs Rigid-Ion Model For The Study Of Point Defects In Uo2
F. Devynck, M. Krack
Proc. Nuclear Materials 2010 Conference (Numath2010), Zkm, Karlsruhe, Germany, October 4-7, 2010

Benchmarking Of Transient Codes Against Cycle 19 Measurements At Leibstadt Nuclear Power Plant (KKL)
C. Aguirre, S. Opel, H. Ferroukhi, G. Grandi, L. Belblidia, M. Thunman, C. Rotander,B-G. Bergdahl, S. Baumgartner, G. Ledergerber
Proc. Int. Conf. Advances in Reactor Physics To Power The Nuclear Renaissance, Physor 2010 Pittsburgh, Usa, May 9-14, 2010

Oecd/Nea Expert Group On Uncertainty Analysis For Criticality Safety Assessment: Current Activities
T. Ivanova, F. Fernex, E. Kolbe, A. Vasiliev, G-S. Lee, S-W. Woo, D. Mennerdahl, Y. Nagaya, J-C. Neuber, A. Hoefer, B. Rearden, D. Mueller, Y. Rugama
Proc. Int. Conf. Advances in Reactor Physics To Power The Nuclear Renaissance, Physor 2010 Pittsburgh, Usa, May 9-14, 2010

A Low-Order Quasidiffusion Discretization Via Linear-Continuous Finite-Elements On Unstructure Triangular Meshes
W. Wieselquist
Proc. Int. Conf. Advances in Reactor Physics To Power The Nuclear Renaissance, Physor 2010 Pittsburgh, Usa, May 9-14, 2010

Lagrangian Simulation of Particle Deposition on an Array of Spheres using RANS-RSM and LES Approaches
A. Dehbi
3^rd CFD4NRS, Bethesda, USA

Outcome of the OECD/SARNET Workshop on In-vessel Coolability
J.C. Birchley, B. Clément, H. Löffler, W. Tromm, A. Amri
4^th ERMSAR, Bologna, Italy

Analysis of Steam Generator Reflux Condensation for Severe Accident Prevention and Mitigation
Y. Liao, J.C. Birchley
4^th ERMSAR, Bologna, Italy

The effect of chemical reactions on primary circuit surface on iodine transport
J. Kalilainen, T. Kärkelä, A. Auvinen, R. Zilliacus, U. Tapper, T. Kajolinna
ANS Conference, Las Vegas, USA

The Effect of Flooding on Aerosol Retention in the Steam Generator Bundle
T.M. Lind, S. Güntay
ANS Conference, Las Vegas, USA

>>Back to top

2005 - 2009

Artioli C, Grasso G, Sarotto M, Krepel J
ELSY neutronic analysis by deterministic and Monte Carlo methods: an innovative concept for the control rod systems
In: Proceedings of ICAPP '09. Vol. 1. International congress on advances in nuclear power plants 2009, ICAPP 2009. Tokyo: Atomic Energy Society of Japan; 2009:718-725.
DORA PSI
Chenu A, Mikityuk K, Chawla R
Modeling of sodium two-phase flow with the trace code
In: Proceedings of the 17th international conference on nuclear engineering, ICONE17. Vol. 1. International conference on nuclear engineering, proceedings, ICONE. New York: American Society of Mechanical Engineers; 2009:803-811. https://doi.org/10.1115/ICONE17-75131
DORA PSI
Girardin G, Blanchet D, Mikityuk K, Rimpault G, Chawla R
Three-dimensional core behaviour analysis of the Gas-cooled Fast Reactor (GFR) during hypothetical control assembly withdrawal accidents
In: Plant operations, maintenance, engineering, modifications and life cycle; component reliability and materials issues; next generation systems. Vol. 1. 17th international conference on nuclear engineering. sine loco: American Society of Mechanical Engineers ASME; 2009:ICONE17-75539 (12 pp.). https://doi.org/10.1115/ICONE17-75539
DORA PSI
Khvostov G
A dynamic model for fission gas release and gaseous swelling integrated into the FALCON fuel analysis and licensing code
In: Water reactor fuel performance meeting 2009: WRFPM top fuel 2009. Vol. 1. Paris: Societe Francaise d'Energie Nucleaire (SFEN); 2009:192-202.
DORA PSI
Kolbe E, Vasiliev A, Ferroukhi H
Assessment of S(α,β) libraries for criticality safety evaluations of wet storage pools by refined trend analyses
In: Proceedings of the nuclear criticality safety division topical meeting on realism, robustness and the nuclear renaissance 2009. American nuclear society - nuclear criticality safety division topical meeting on realism, robustness and the nuclear renaissance 2009. Red Hook: Curran; 2009:13-23.
DORA PSI
Krepel J, Sarotto M, Mikityuk K, Artioli C
EFIT fuel cycle analysis with the EQL3D procedure
In: Proceedings of ICAPP '09. Vol. 3. International congress on advances in nuclear power plants 2009, ICAPP 2009. Tokyo: Atomic Energy Society of Japan; 2009:1996-2004.
DORA PSI
Krepel J, Mikityuk K, Sun K, Rimpault G
SFR equilibrium cycle analysis with the EQL3D procedure
In: Proceedings of ICAPP '09. Vol. 1. International congress on advances in nuclear power plants 2009, ICAPP 2009. Tokyo: Atomic Energy Society of Japan; 2009:749-758.
DORA PSI
Kröhnert H, Murphy MF, Perret G, Chawla R
Utilization of freshly induced high-energy gamma-ray activity as a measure of fission rates in re-irradiated burnt UO₂ fuel
In: Proceedings of the 2009 1st international conference on advancements in nuclear instrumentation, measurement methods and their applications. ANIMMA 2009 - 2009 1st international conference on advancements in nuclear instrumentation, measurement methods and their applications. Piscataway: IEEE; 2009:(6 pp.). https://doi.org/10.1109/ANIMMA.2009.5503809
DORA PSI
Leyer S, Maisberger F, Schaub B, Brettschuh W, Doll M, Wich M, et al.
Full scale quasi steady state component tests of the SWR 1000 emergency condenser at the INKA test facility
In: Proceedings of ICAPP '09. Vol. 2. International congress on advances in nuclear power plants 2009, ICAPP 2009. Tokyo: Atomic Energy Society of Japan; 2009:1627-1628.
DORA PSI
Mikityuk K
Fast code system: review of recent developments and near-future plans
In: Proceedings of the 17th international conference on nuclear engineering, ICONE17. Vol. 1. International conference on nuclear engineering, proceedings, ICONE. New York: American Society of Mechanical Engineers; 2009:823-829. https://doi.org/10.1115/ICONE17-75152
DORA PSI
Pelloni S, Mikityuk K, Epiney A
A new cross-section generation model in the fast code system and its application to the Gen-IV Gas-cooled Fast Reactor
In: Proceedings of the international conference on mathematics, computational methods and reactor physics 2009 (M and C 2009). Vol. 2. American nuclear society - international conference on mathematics, computational methods and reactor physics 2009, M and C 2009. La Grange Park: American Nuclear Society; 2009:801-812.
DORA PSI
Poette C, Brun-Magaud V, Morin F, Pignatel J-F, Stainsby R, Mikityuk K
ALLEGRO: The European Gas Fast Reactor demonstrator project
In: Proceedings of the 17th international conference on nuclear engineering, ICONE17. Vol. 2. International conference on nuclear engineering, proceedings, ICONE. ; 2009:815-822. https://doi.org/10.1115/ICONE17-75326
DORA PSI
Bertolotto D, Manera A, Smith B, Prasser H-M, Chawla R
Single-phase mixing studies by means of a directly coupled CFD/system-code tool
In: Proceedings of the international conference on the physics of reactors "nuclear power: a sustainable resource". Vol. 3. International conference on the physics of reactors 2008, PHYSOR 08. Villigen: Paul Scherrer Institut; 2008:2012-2020.
DORA PSI
Blanchet D, Pelloni S, Coddington P, Mikityuk K
Analysis of reactivity insertion transients in the ETDR - a small gas cooled fast reactor
In: Proceedings of the international conference on the physics of reactors "nuclear power: a sustainable resource". Vol. 3. International conference on the physics of reactors 2008, PHYSOR 08. Villigen: Paul Scherrer Institut; 2008:2205-2212.
DORA PSI
Bubelis E, Castelliti D, Coddington P, Dor I, Fouillet C, de Geus E, et al.
A GFR benchmark comparison of transient analysis codes based on the ETDR concept
In: Proceedings of ICAPP 2007. Vol. 3. Societe francaise d'energie nucleaire - international congress on advances in nuclear power plants - ICAPP 2007, "the nuclear renaissance at work". Paris: Societe Francaise d'Energie Nucleaire; 2008:7340 (10 pp.).
DORA PSI
Dumaz P, Epiney A, Alpy N, Broxtermann P, Malo JY, Tosello A
Studies of unprotected transients and alternative decay heat removal system for the Gas cooled Fast Reactor (GFR)
In: Proceedings of ICAPP '08. Vol. 1. International conference on advances in nuclear power plants, ICAPP 2008. La Grange Park: American Nuclear Society; 2008:219-227.
DORA PSI
Epiney A, Dumaz P, Coddington P, Mikityuk K, Chawla R
Comparative transient analysis of the 2400MWth GFR with the TRACE and CATHARE codes
In: Proceedings of the International conference on the physics of reactors "nuclear power: a sustainable resource". Vol. 3. International conference on the physics of reactors 2008, PHYSOR 08. Villigen: Paul Scherrer Institut; 2008:2236-2243.
DORA PSI
Epiney A, Coddington P, Mikityuk K, Chawla R
New analysis of the EIR GFR thermal-hydraulic experiments
In: Proceedings of the international conference on the physics of reactors "nuclear power: a sustainable resource". Vol. 4. International conference on the physics of reactors 2008, PHYSOR 08. Villigen: Paul Scherrer Institut; 2008:3115-3122.
DORA PSI
Ferroukhi H, Zerkak O, Chawla R
Comparative study of CORETRAN and SIMULATE-3K for main steam line break analyses
In: Proceedings of the international conference on the physics of reactors "nuclear power: a sustainable resource". Vol. 3. International conference on the physics of reactors 2008, PHYSOR 08. Villigen: Paul Scherrer Institut; 2008:1825-1832.
DORA PSI
Ferroukhi H, Hofer K, Hollard J-M, Vasiliev A, Zimmermann MA
Core modelling and analysis of the Swiss Nuclear Power Plants for qualified R&D applications
In: Proceedings of the international conference on the physics of reactors "nuclear power: a sustainable resource". Vol. 2. International conference on the physics of reactors 2008, PHYSOR 08. Villigen: Paul Scherrer Institut; 2008:1274-1281.
DORA PSI
Ferroukhi H, Hollard J-M, Zimmermann MA, Chawla R
Estimation of the fast neutron fluence at control rod tips using a 3-D diffusion/2-D transport calculation scheme
In: Proceedings of the international conference on the physics of reactors "nuclear power: a sustainable resource". Vol. 2. International conference on the physics of reactors 2008, PHYSOR 08. Villigen: Paul Scherrer Institut; 2008:997-1004.
DORA PSI
Girardin G, Mikityuk K, Coddington P, Chawla R
A 3D full-core coupled thermal-hydraulics/kinetics TRACE/PARCS model of the 2400 MWth generation IV gas-cooled fast reactor
In: Proceedings of the international conference on the physics of reactors "nuclear power: a sustainable resource". Vol. 3. International conference on the physics of reactors 2008, PHYSOR 08. Villigen: Paul Scherrer Institut; 2008:2273-2280.
DORA PSI
Girardin G, Rimpault G, Coddington P, Chawla R
Control rod shadowing and anti-shadowing effects in a large gas-cooled fast reactor
In: Proceedings of ICAPP 2007. Vol. 3. Societe francaise d'energie nucleaire - international congress on advances in nuclear power plants - ICAPP 2007, "the nuclear renaissance at work". Paris: Societe Francaise d'Energie Nucleaire; 2008:1858-1865.
DORA PSI
Grimm P, Murphy MF, Jatuff F, Seiler R
Analysis of reactivity worths of highly-burnt PWR fuel samples measured in LWR-PROTEUS Phase II
In: Proceedings of the international conference on the physics of reactors "nuclear power: a sustainable resource". Vol. 4. International conference on the physics of reactors 2008, PHYSOR 08. Villigen: Paul Scherrer Institut; 2008:2801-2806.
DORA PSI
Jaruff F, Perret G, Murphy M, Grimm P, Seiler R, Chawla R
Impact of newly-measured gadolinium cross sections on BWR fuel rod reaction rate distributions
In: Proceedings of the international conference on the physics of reactors "nuclear power: a sustainable resource". Vol. 1. International conference on the physics of reactors 2008, PHYSOR 08. Villigen: Paul Scherrer Institut; 2008:266-272.
DORA PSI
Joneja OP, Perret G, Grimm P, Jatuff F, Chawla R
MCNP analysis of generic configurations in the context of the LIFE@PROTEUS experiments
In: Proceedings of the international conference on the physics of reactors "nuclear power: a sustainable resource". Vol. 1. International conference on the physics of reactors 2008, PHYSOR 08. Villigen: Paul Scherrer Institut; 2008:687-694.
DORA PSI
Khvostov G, Zimmermann MA, Stoenescu R, Ledergerber G
Definition of optimal parameters of fuel rod design and test conditions for the high temperature LOCA experiment IFA-650.7 using the FALCON fuel behaviour code
In: Proceedings of the fuels & materials sessions. Vol. HPR-369. Sine loco: Institutt for energiteknikk; 2008:(20 pp.).
DORA PSI
Khvostov G, Zimmermann MA, Sugiyama T, Fuketa T
On the use of the FALCON code for modeling the behaviour of high burn-up BWR fuel during the LS-1 pulse-irradiation test
In: Nuclear power: a sustainable resource: PHYSOR'08, International conference on the physics of reactors, 14-19 September 2008, Interlaken, Switzerland ; proceedings. Villigen: Paul Scherrer Institut PSI; 2008:1-8.
DORA PSI
Khvostov G, Zimmermann MA, Ledergerber G, Kolstad E, Montgomery RO
Parametric study of the behaviour of a pre-irradiated BWR fuel rod under conditions of LOCA simulated in the Halden in-pile test system with the FALCON code
In: Water reactor fuel performance meeting 2008. Daejeon, Korea; Tokyo, Japan: Korean Nuclear Society (KNS); Atomic Energy Society of Japan; 2008:8099 (10 pp.).
DORA PSI
Kolbe E, Vasiliev A, Zimmermann MA
Validation of standard neutron data libraries for LWR storage pools and transport casks criticality safety evaluations
In: ND 2007 - international conference on nuclear data for science and technology 2007. Les Ulis Cedex A, France: EDP Sciences; 2008:799-802. https://doi.org/10.1051/ndata:07441
DORA PSI
Krepel J, Pelloni S, Mikityuk K
Equilibrium cycle analysis of a gas cooled fast reactor with the EQL3D procedure
In: Proceedings of the International conference on the physics of reactors "nuclear power: a sustainable resource". Vol. 3. International conference on the physics of reactors 2008, PHYSOR 08. Villigen: Paul Scherrer Institut; 2008:2221-2228.
DORA PSI
Malo JY, Mizuno T, Wei TYC, Mitchell C, Coddington P
GIF GFR end-of-exploratory phase design and safety studies
In: Proceedings of the international conference on the physics of reactors "nuclear power: a sustainable resource". Vol. 3. International conference on the physics of reactors 2008, PHYSOR 08. Villigen: Paul Scherrer Institut; 2008:2229-2235.
DORA PSI
Pelloni S, Krepel J, Mikityuk K
EQL3D: Methodology for simulation of equilibrium cycle for advanced fast reactors
In: Proceedings of the international conference on the physics of reactors "nuclear power: a sustainable resource". Vol. 3. International conference on the physics of reactors 2008, PHYSOR 08. Villigen: Paul Scherrer Institut; 2008:2173-2180.
DORA PSI
Pelloni S, Bubelis E, Coddington P
Steady-state and transient neutronic and thermal-hydraulic analysis of ETDR using the FAST code system
In: Proceedings of ICAPP 2007. Vol. 4. Societe francaise d'energie nucleaire - international congress on advances in nuclear power plants - ICAPP 2007, "the nuclear renaissance at work". Paris: Societe Francaise d'Energie Nucleaire; 2008:7440 (8 pp.).
DORA PSI
Perret G, Murphy MF, Jatuff F, Chawla R
Fission rate distribution at the 84-pin radial section of a SVEA-96 Optima2 BWR assembly
In: Proceedings of the international conference on the physics of reactors "nuclear power: a sustainable resource". Vol. 4. International conference on the physics of reactors 2008, PHYSOR 08. Villigen: Paul Scherrer Institut; 2008:2715-2720.
DORA PSI
Petkevich P, Mikityuk K, Coddington P, Chawla R
A 2D transient model for gas-cooled fast reactor plate-type fuel
In: Proceedings of ICAPP '07. Vol. 3. Societe francaise d'energie nucleaire - international congress on advances in nuclear power plants - ICAPP 2007, "The nuclear renaissance at work". Paris: Societe Francaise d'Energie Nucleaire; 2008:1866-1872.
DORA PSI
Petkevich P, Mikityuk K, Coddington P, Chawla R
GFR transient analysis employing a 2D thermomechanical model for the plate-type fuel
In: Proceedings of the international conference on the physics of reactors "nuclear power: a sustainable resource". Vol. 3. International conference on the physics of reactors 2008, PHYSOR 08. Villigen: Paul Scherrer Institut; 2008:2252-2259.
DORA PSI
Poette C, Brun-Magaud V, Morin F, Dor I, Pignatel J-F, Bertrand F, et al.
ETDR, the European Union's experimental gas-cooled fast reactor project
In: Proceedings of the international conference on the physics of reactors "nuclear power: a sustainable resource". Vol. 3. International conference on the physics of reactors 2008, PHYSOR 08. Villigen: Paul Scherrer Institut; 2008:2197-2204.
DORA PSI
Vasiliev A, Ferroukhi H, Zimmermann MA, Kolbe E
On the observation of discrepancies in the ¹⁶O(n,α) data between different evaluated nuclear data files
In: ND 2007 - international conference on nuclear data for science and technology 2007. Les Ulis Cedex A, France: EDP Sciences; 2008:965-968. https://doi.org/10.1051/ndata:07445
DORA PSI
Vasiliev A, Ferroukhi H, Kolbe E, Zimmermann MA
On the use of importance factors from Monte Carlo calculations for efficient fast neutron fluence prediction
In: Proceedings of the international conference on the physics of reactors "nuclear power: a sustainable resource". Vol. 2. International conference on the physics of reactors 2008, PHYSOR 08. Villigen: Paul Scherrer Institut; 2008:856-863.
DORA PSI
Zerkak O, Ferroukhi H
Effects of the core inlet mixing modelling on a main steam line break analysis at hot full power
In: Proceedings of the international conference on the physics of reactors "nuclear power: a sustainable resource". Vol. 3. International conference on the physics of reactors 2008, PHYSOR 08. Villigen: Paul Scherrer Institut; 2008:1943-1950.
DORA PSI
Barten W, Manera A, Macian-Juan R
Assessment of the capability of the trace code to model the propagation of linear acoustic pressure waves in one-dimensional flows
In: 12th international topical meeting on nuclear reactor thermal hydraulics (NURETH-12). Westmont: American Nuclear Society; 2007:652-665.
DORA PSI
Ferroukhi H, Hollard JM, Zerkak O, Coddington P
PWR cell calculations using APOLLO-2 within the NURESIM benchmark framework
In: Vol. 97. Transactions of the American Nuclear Society. Westmont: American Nuclear Society; 2007:703-704. https://www.ans.org/pubs/transactions/article-7751/.
DORA PSI
Hellwig C, Horvath MI, Blair PR, Chawla R, Günther D
Fission gas distribution and behavior in the high burn-up structure
In: LWR fuel performance meeting/top fuel 2007. Westmont: American Nuclear Society; 2007:291-300.
DORA PSI
Khvostov G, Romano A, Zimmermann MA
Modeling the effects of axial fuel relocation in the IFA-650.4 LOCA test
Presented at: Enlarged Halden programme group meeting 2007; March 11-16, 2007; Storefjell, Norway.
DORA PSI
Manera A, Macian R
Assessment of trace film condensation models with and without non-condensable gases
In: 12th international topical meeting on nuclear reactor thermal hydraulics (NURETH-12). Westmont: American Nuclear Society; 2007:254-268.
DORA PSI
Rohde M, Marcel CP, Manera A, van der Hagen THJJ, Shiralkar B
Experimental and numerical investigations on the ESBWR stability performance
In: 12th international topical meeting on nuclear reactor thermal hydraulics (NURETH-12). Westmont: American Nuclear Society; 2007:099 (20 pp.).
DORA PSI
Zboray R, Manera A, Niceno B, Prasser H-M
Investigations on mixing phenomena in single-phase flows in a T-junction geometry
In: 12th international topical meeting on nuclear reactor thermal hydraulics (NURETH-12). Westmont: American Nuclear Society; 2007:830-849.
DORA PSI
Zerkak O, Coddington P, Crouzet N, Royer E, Jimenez J, Cuervo D
LWR multi-physics developments and applications within the framework of the NURESIM European project
In: Joint international topical meeting on mathematics & computations and supercomputing in nuclear applications (M & C + SNA 2007). Vol. 4. La Grange Park: American Nuclear Society; 2007:2178-2199.
DORA PSI
Bubelis E, Coddington P, Leung W
Pre-test analysis of the MEGAPIE spallation source target cooling loop using the TRAC/AAA code
In: Proceedings of ICAPP '06. Vol. 2006. Proceedings of the 2006 international congress on advances in nuclear power plants, ICAPP'06. La Grange Park: American Nuclear Society; 2006:452-461.
DORA PSI
Caruso S, Murphy M, Jatuff F, Chawla R
Non-invasive characterization of burnup for PWR spent fuel rods with burnups > 80 GWd/t
In: Proceedings of ICAPP '06. Vol. 2006. Proceedings of the 2006 international congress on advances in nuclear power plants, ICAPP'06. La Grange Park: American Nuclear Society; 2006:2020-2027.
DORA PSI
Girardin G, Pelloni S, Coddington P, Chawla R
Comparative analysis of the reference GCFR-PROTEUS MOX lattice with MCNPX-25e and ERANOS-2.0 in conjunction with modern nuclear data libraries
In: PHYSOR 2006 : advances in nuclear analysis and simulation : American nuclear society's topical meeting on reactor physics. Vol. 2006. PHYSOR-2006 - American nuclear society's topical meeting on reactor physics. La Grange: American Nuclear Society; 2006:(9 pp.).
DORA PSI
Grimm P, Günther-Leopold I, Kobler Waldis J, Berger HD, Krouthén J
Burnup calculations and chemical analysis of irradiated fuel samples studied in LWR-PROTEUS phase II
In: PHYSOR-2006 - American nuclear society's topical meeting on reactor physics. Advances in nuclear analysis and simulation. Vol. 2006. PHYSOR-2006 - American nuclear society's topical meeting on reactor physics. La Grange: American Nuclear Society; 2006:(3 pp.).
DORA PSI
Jasiulevicius A, Macian-Juan R
Impact of different correlations on TRACEv4.160 predicted critical heat flux
In: Proceedings of ICAPP '06. Vol. 2006. Proceedings of the 2006 international congress on advances in nuclear power plants, ICAPP'06. La Grange Park: American Nuclear Society; 2006:1608-1615.
DORA PSI
Jasiulevicius A, Zerkak O, Macian-Juan R
Investigation of heat transfer mechanisms under shutdown plant conditions with TRACEv4.160
In: Proceedings of ICAPP'06. Vol. 2006. Proceedings of the 2006 international congress on advances in nuclear power plants, ICAPP'06. La Grange Park: American Nuclear Society; 2006:1820-1828.
DORA PSI
Jasiulevicius A, Macian-Juan R
Predictions of critical heat flux in annular pipes with TRACE V4.160 code
In: International conference on nuclear engineering, proceedings, ICONE. Vol. 2006. International conference on nuclear engineering, proceedings, ICONE. New York: American Society of Mechanical Engineers; 2006:243-250. https://doi.org/10.1115/ICONE14-89253
DORA PSI
Jasiulevicius A, Macian-Juan R
Steady state film boiling heat transfer simulated with trace V4.160
In: Proceedings of ICONE 14. Vol. 2006. International conference on nuclear engineering, proceedings, ICONE. New York: American Society of Mechanical Engineers; 2006:531-539. https://doi.org/10.1115/ICONE14-89494
DORA PSI
Kolbe E, Vasiliev A, Zimmermann MA
Assessment of standard point-wise neutron data libraries for criticality safety analysis with a Monte Carlo code
In: Proceedings of the American nuclear society's topical meeting on reactor physics. Vol. 2006. PHYSOR-2006 - American nuclear society's topical meeting on reactor physics. La Grange Park: American Nuclear Society; 2006:D081 (10 pp.).
DORA PSI
Lebrat JF, Plaschy M, Tommasi J, Suteau C, Plisson-Rieunier D, De Saint Jean C
Comparative analysis of selected aspects of the muse-4 experiments with the JEF-2.2 and JEFF-3.1 libraries
In: Vol. 2006. PHYSOR-2006 - American nuclear society's topical meeting on reactor physics. La Grange Park: American Nuclear Society; 2006:3052-3061.
DORA PSI
Mitchell C, Poette C, Peers K, Coddington P, Somers J, Van-Goethem G
GCFR: the European Union's gas cooled fast reactor project
In: Proceedings of ICAPP '06. Vol. 2006. Proceedings of the 2006 international congress on advances in nuclear power plants, ICAPP'06. La Grange Park: American Nuclear Society; 2006:540-548.
DORA PSI
Murphy MF, Plaschy M, Jatuff F, Bergmann U, Chawla R
Fission and capture rate measurements in a SVEA-96 optima2 BWR assembly compared with MCNPX predictions
In: American nuclear society's topical meeting on reactor physics. Vol. 2006. PHYSOR-2006 - American nuclear society's topical meeting on reactor physics. La Grange: American Nuclear Society; 2006:1169-1176.
DORA PSI
Petkevich P, Mikityuk K, Coddington P, Pelloni S, Chawla R
Comparative transient analysis of a gas-cooled fast reactor for different fuel types
In: Proceedings of ICAPP '06. Vol. 2006. Proceedings of the 2006 international congress on advances in nuclear power plants, ICAPP'06. La Grange Park: American Nuclear Society; 2006:549-559.
DORA PSI
Plaschy M, Destouches C, Chawla R, Beretz D, Mellier F, Servière H, et al.
Determination of adjusted neutron spectra in different MUSE configurations by unfolding techniques
In: Vehar DW, Gilliam DG, Adams JM, eds. Reactor dosimetry. 12th international symposium. Vol. 1490. West Conshohocken, PA: ASTM International; 2006:55-65. https://doi.org/10.1520/STP45426S
DORA PSI
Plaschy M, Murphy M, Jatuff F, Seiler R, Chawla R
Experimental critical loadings and control rod worths in LWR-PROTEUS configurations compared with MCNPX results
In: PHYSOR 2006 : advances in nuclear analysis and simulation : American nuclear society's topical meeting on reactor physics. Vol. 2006. PHYSOR-2006 - American nuclear society's topical meeting on reactor physics. La Grange: American Nuclear Society; 2006:A093 (10 pp.).
DORA PSI
Vasiliev A, Ferroukhi H, Zimmermann MA
CASMO-4/SIMULATE-3/MCNPX analysis of a reactor pressure vessel scraping test
In: Proceedings of the American nuclear society's topical meeting on reactor physics. Vol. 2006. PHYSOR-2006 - American nuclear society's topical meeting on reactor physics. La Grange Park: American Nuclear Society; 2006:B136 (10 pp.).
DORA PSI
Vinai P, Macian R, Chawla R
A methodology for the quantification of uncertainty in best estimate code physical models
In: Proceedings of ICAPP '06. Vol. 2006. Proceedings of the 2006 international congress on advances in nuclear power plants, ICAPP'06. La Grange Park: American Nuclear Society; 2006:1087-1098.
DORA PSI
Vollaire J, Plaschy M, Jatuff F, Chawla R
Determination of β_effusing MCNP-4C2 and application to the CROCUS and PROTEUS reactors
In: American nuclear society's topical meeting on reactor physics. Vol. 2006. PHYSOR-2006 - American nuclear society's topical meeting on reactor physics. La Grange: American Nuclear Society; 2006:1254-1259.
DORA PSI
da Cruz DF, Hogenbirk A, Bosq JC, Rimpault G, Prulhiere G, Morris P, et al.
Neutronic benchmark on the 2400 MW gas-cooled fast reactor design
In: PHYSOR 2006 : advances in nuclear analysis and simulation : American nuclear society's topical meeting on reactor physics. Vol. 2006. PHYSOR-2006 - American nuclear society's topical meeting on reactor physics. La Grange: American Nuclear Society; 2006:D126 (10 pp.).
DORA PSI

Advanced Processing Of Gas-Liquid Piv Measurements In 3d Bubble Plume
M Simianio, R Zboray, F Decachard, D Lakehal, G Yadigaroglu
Nureth 11: Proceedings Of The 11th International Topical Meeting On Nuclear Reactor Thermal-Hydraulics 1, 1 (2006).

Trace And Relap5 Thermal-Hydraulic Analysis On Boron Dilution Tests At The Pkl Facility
J. Freixa, A. Manera
Proc. 13th Int. **Topical. Meetg. On Nuclear Reactor Thermal Hydraulics Nureth-13, Kanazawa, Japan September 27-October 2, 2009

Effect Of Power Uprate On Exceedance Frequency During Mbloca With Minimum Specifications For Success
T-W. Kim, A. Manera, M.A. Zimmermann, V.N. Dang
Proc. 13th Int. **Topical. Meetg. On Nuclear Reactor Thermal Hydraulics Nureth-13, Kanazawa, Japan September 27-October 2, 2009

Toward The Prediction Of Temperature Fluctuations By Means Of Steady Rans For The Estimation Of Thermal Fatigue
A. Manera, H.M. Prasser, R. Lechner, T. Frank
Proc. 13th Int. **Topical. Meetg. On Nuclear Reactor Thermal Hydraulics Nureth-13, Kanazawa, Japan September 27-October 2, 2009

Simulation Of Reflood Experiments Using The Best-Estimate Thermal-Hydraulic Code Trace
K. Nikitin, A. Manera
Proc. 13th Int. **Topical. Meetg. On Nuclear Reactor Thermal Hydraulics Nureth-13, Kanazawa, Japan September 27-October 2, 2009

Assessment Of S(Alpha,Beta) Libraries For Criticality Safety Evaluations Of Wet Storage Pools By Refined Trend Analyses
E. Kolbe, A. Vasiliev, H. Ferroukhi
Proc. Nuclear Criticality Safety Division **Topical Meeting Ncsd 2009, Richland, Washington, Us, September 13-17, 2009

Parametric Study Of Fuel Rod Behaviour During The Ria Using The Modified Falcon Code
G. Khvostov, M.A. Zimmermann, G. Ledergerber
Proc. Oecd/Nea Workshop On Nuclear Fuel Behaviour During Reactivity Initiated Accidents, Paris, France, September 9-11, 2009

Towards Quantification Of Plant Safety Margins - A Status Report
M.A. Zimmermann, T-W. Kim, S. Laroche, A. Ui, S. Ebata, J-J. Jeong, H-G. Lim, S-H. Ahn, M. Gavrilas, J. Hortal
Proc. 13th Int. Topical. Meetg. On Nuclear Reactor Thermal Hydraulics Nureth-13, Kanazawa, Japan , September 27-October 2, 2009

Insights Into Fuel Rod Performance Codes During Ramps: Results Of A Code Benchmark Based On The Scip Project
L.E. Herranz, I. Vallejo, G. Khvostov, J. Sercombe, G. Zhou
Proc. of Top Fuel 2009, Paris, France, September 2009

A Quasidiffusion Method For Unstructured Quadrilateral Meshes In 2d Xy Geometry
W.A. Wieselquist, D. Y. Anistratov
Proc. Int. Conf. On Mathematics, Computational Methods And Reactor Physics (Mc2009), Saratoga Springs, New York, May 3-7, 2009

Direct Numerical Simulation of Buoyancy Driven Turbulence inside a Cubic Cavity
R. Puragliesi, A. Dehbi, E. Leriche, A. Soldati, M. Deville
Conference on Turbulence and Interactions, La Martinique

Post-Test Analysis of the Quench-13 Bundle Test Including an Ag-In-Cd Absorber Rod
J.C. Birchley, B.S. Jäckel, T.J. Haste, M. Steinbrück, J. Stuckert
ICAPP, Tokyo, Japan

Influence of corium oxidation on fission product release from molten pool
S.V. Bechta, E.V. Krushinov, S.A. Vitol, V.B. Khabensky, S.Y. Kotova, A.A. Sulatskiy, R.A. Kosarevskiy, V.V. Gusarov, V.I. Almyashev, G. Ducros, C. Journeau, D. Bottomley, B. Clément, L.E. Herranz, S. Güntay, K. Trambauer, A. Auvinen
ICAPP, Tokyo, Japan

Results of the QUENCH-13 Reflood Bundle Test with Incorporation of an AgInCd Absorber Rod
L. Sepold, T.M. Lind, A. Pintér Csordás, U. Stegmaier, M. Steinbrück, J. Stuckert
ICAPP, Tokyo, Japan

Noncondensable Gas Effect on Film Condensation of Boundary Layer Flow in the Entire Mixed Convection Regime
Y. Liao, S. Güntay
13^th NURETH Conference, Kanazawa, Japan

The Once-Through Mode of Steam Generator Reflux Condensation in Loss of Coolant Accident Scenarios
Y. Liao, S. Güntay, D.J. Suckow
13^th NURETH Conference, Kanazawa, Japan

LWR Containment Safety Research in PANDA
D. Paladino, M. Huggenberger, M. Andreani, S. Gupta, S. Güntay, J. Dreier, H.-M. Prasser
ICAPP, Anaheim, USA

Single-Phase Mixing Studies By Means Of A Directly Coupled CFD/System-Code Tool
D. Bertolotto , A. Manera, B.L. Smith, H.M. Prasser, R. Chawla
Proc.Int.Conf.On The Physics of Reactors, Physor'08, September 14-19, 2008, Interlaken, Switzerland (Cd-Rom,Fp412)

CFD Simulations Of A Single-Phase Mixing Experiment
D. Bertolotto , A. Manera, B.L. Smith, H.M. Prasser, R. Chawla
Proc.Int.Youth. Nuclear Congress Iync 2008 September 20-26, 2008, Interlaken, Switzerland

Estimation Of The Fast Neutron Fluence At Control Rod Tips Using A 3-D Diffusion/2-D Transport Calculation Scheme
H. Ferroukhi H., J-M. Hollard, M.A. Zimmermann, R. Chawla
Proc.Int.Conf.On The Physics of Reactors, Physor'08, September 14-19, 2008, Interlaken, Switzerland

Core Modelling And Analysis Of The Swiss Nuclear Power Plants For Qualified R&D Applications
H. Ferroukhi , K. Hofer, J-M. Hollard, A. Vasiliev, M.A. Zimmermann
Proc.Int.Conf.On The Physics of Reactors, Physor'08, September 14-19, 2008, Interlaken, Switzerland

Comparative Study Of Coretran And Simulate-3k For Main Steam Line Break Analyses
H. Ferroukhi , O. Zerkak, R. Chawla
Proc.Int.Conf.On The Physics of Reactors, Physor'08, September 14-19, 2008, Interlaken, Switzerland

On The Use Of Importance Factors From Monte Carlo Calculations For Efficient Fast Neutron Fluence Prediction
A. Vasiliev, H. Ferroukhi, E. Kolbe, M.A. Zimmermann
Proc.Int.Conf.On The Physics of Reactors, Physor'08, September 14-19, 2008, Interlaken, Switzerland

Propagation Of Void Fraction Uncertainty Measures In The Retran-3d Simulation Of The Peach Bottom Turbine Trip
P. Vinai, R. Macian-Juan, R. Chawla
Proc.Int.Conf.On The Physics of Reactors, Physor'08, September 14-19, 2008, Interlaken, Switzerland (Fp607)

Effects Of The Core Inlet Mixing Modelling On A Main Steam Line Break Analysis At Hot Full Power
O. Zerkak, H. Ferroukhi
Proc.Int.Conf.On The Physics of Reactors, Physor'08, September 14-19, 2008, Interlaken, Switzerland

Effect Of Longitudinal Pitch On The Heat Transfer Characteristics Of Aligned Tube Banks In Crossflow
T-W. Kim
Proc. Nuthos-7, 5-9 October 2008, Seoul, Korea

Code-To-Code Comparison For Blowdown Transients At Supercritical Conditions
A. Manera, O. Antoni
Proc. Jahrestagung Kerntechnik 2008, 27-29 May 2008, Hamburg, Germany

Assessment against DNS data of a coupled CFD-stochastic model for particle dispersion in turbulent channel flows
A. Dehbi
2^nd CFD4NRS, Grenoble, France

Status of Studies on High-Temperature Oxidation and Quench Behaviour of Zircaloy-4 and E110 Cladding Alloys
M. Steinbrück, J.C. Birchley, A.V. Goryachev, M. Grosse, T.J. Haste, Z. Hozer, A.E. Kisselev, V.I. Nalivaev, V.P. Semishkin, L. Sepold, J. Stuckert, N. Vér, M.S. Veshchunov
3^rd ERMSAR, Nesseber, Bulgaria

Modelling of Accelerated Cladding Degradation in Air for Severe Accident Codes
C. Bals, E. Beuzet, J.C. Birchley, O. Coindreau, S. Ederli, T.J. Haste, T. Hollands, M.K. Koch, J.-S. Lamy, K. Trambauer
3^rd ERMSAR, Nesseber, Bulgaria

Progress on B₄C modelling in Severe Accident Codes in the frame of SARNET network of excellence - Applications to Phebus and Quench experiments
G. Repetto, O. De Luze, K. Trambauer, H. Austregesilo, J.C. Birchley, J.S. Lamy, B. Malivernay
3^rd ERMSAR, Nesseber, Bulgaria

Understanding the behaviour of absorber elements in silver-indium-cadmium control rods during PWR severe accident sequences
R. Dubourg, H. Austregesilo, C. Bals, M. Barrachin, J.C. Birchley, T.J. Haste, J.S. Lamy, T.M. Lind, B. Maliverney, C. Marchetto, A. Pinter, M. Steinbrück, J. Stuckert, K. Trambauer, A. Vimi
3^rd ERMSAR, Nesseber, Bulgaria

Progress in understanding key aerosol issues
L.E. Herranz, J. Ball, A. Auvinen, D. Bottomley, A. Dehbi, C. Housiadas, P. Piluso, V. Layly, F. Parozzi, M. Reeks
3^rd ERMSAR, Nesseber, Bulgaria

Ruthenium Behaviour under Air Ingress Conditions: Main Achievements in the SARNET Project
P. Giordano, A. Auvinen, G. Brillant, J. Colombani, N. Davidovich, R. Dickson, T.J. Haste, T. Kärkelä, J.S. Lamy, C. Mun, D. Ohai, Y. Pontillon, M. Steinbrück, N. Vér
3^rd ERMSAR, Nesseber, Bulgaria

Summary of SARNET achievements
T. Albiol, T.J. Haste, J.-P. van Dorsselaere, C. Journeau, L. Meyer, B. Chaumont, B.R. Sehgal, B. Schwinges, D. Beraha, A. Annunziato, R. Zeyen
3^rd ERMSAR, Nesseber, Bulgaria

Status of SARNET 2
T. Albiol, J.-P. van Dorsselaere, W. Tromm, C. Journeau, I. Kljenak, T.J. Haste, B.R. Sehgal, D. Beraha
3^rd ERMSAR, Nesseber, Bulgaria

Analysis of Station Blackout in the Gösgen Nuclear Plant
T.J. Haste, J.C. Birchley, J.-U. Klügel
ICAPP, Anaheim, USA

Pre-Test Calculational Support for the QUENCH-13 Experiment
T.J. Haste, J.C. Birchley, J.-S. Lamy, B. Maliverney, H. Austregesilo, C. Bals, K. Trambauer, M. Steinbrück, J. Stuckert
ICAPP, Anaheim, USA

Experimental and Post-Test Calculation Results of the Integral Reflood Test QUENCH-12 with a VVER-type Bundle
J. Stuckert, J.C. Birchley, M. Große, T.J. Haste, L. Sepold, M. Steinbrück
ICAPP, Anaheim, USA

MELCOR Validation against a PUMA Facility Main Steam Line Break Integral Test
Y. Liao, K. Vierow, J.T. Han
ICAPP, Anaheim, USA

Post-Test Analysis of the QUENCH-13 Experiment
J.C. Birchley, H. Austregesilo, C. Bals, R. Dubourg, T.J. Haste, J.S. Lamy, T.M. Lind, B. Maliverney, C. Marchetto, A. Pinter, M. Steinbrück, J. Stuckert, K. Trambauer
17^th NENE Conference, Portoroz, Slovenia
http://www.nss.si/proc/port2008/pdf/503.pdf

Analysis of the PHÉBUS FPT3 Core Degradation Using severe Accident Codes ICARE/CATHARE, ATHLET-CD, MELCOR
G. Repetto, J.C. Birchley
ANS Conference, Anaheim, USA

A Probabilistic model using artist data for analysis of SGTR fission product release fraction
Y. Liao, S. Guentay, A. Dehbi
ANS Conference, Anaheim, USA

Fluent simulation of separator and dryer aerodynamics and comparison with data
M. Ogino, R. Kapulla, A. Dehbi
ANS Conference, Anaheim, USA

Droplet Retention and Velocity field in a Steam Generator
R. Kapulla, S. Danner, S. Guentay
ANS Conference, Anaheim, USA

CFD simulation of ARTIST break stage and comparisons with measured data
T. Berg, J. Bredberg, D.J. Suckow
ANS Conference, Anaheim, USA

Results from the ARTIST flooded bundle tests
A. Dehbi, D.J. Suckow, S. Güntay
ANS Conference, Anaheim, USA

Particle retention in ARTIST dry bundle tests
T.M. Lind, D.J. Suckow, S. Güntay
ANS Conference, Anaheim, USA

Numerical modeling of flow in dry secondary side of steam generator
T. Berg, J. Bredberg, A. Dehbi, J. Bredberg
ANS Conference, Anaheim, USA

Fission Product release boundary conditions for SGTR-initiated severe accident
Y. Liao, S. Güntay
ANS Conference, Anaheim, USA

Introduction to the ARTIST program
S. Güntay, A. Dehbi, D.J. Suckow
ANS Conference, Anaheim, USA

Assessment Of The Capability Of The Trace Code To Model Propagation Of Linear Acoustic Pressure Waves In One-Dimensional Flow
W. Barten, A. Manera, Juan. Macian,
Nureth-12, 30 September- 4 October 2007, Pittsburgh, Usa

PWR cell Calculations Using Apollo-2 Within The Nuresim Benchmark Framework
H. Ferroukhi, J. Hollard, Zerkak. M, Coddington. O,
Trans.American.Nuclear.Society, Vol. 97, Pp 703-704 (2007)

Assessment Of The Chf Models In Trace Code Against Rod Bundle Experimental Data
A. Jasiulevicius, Juan. Macian,
Icone-15, 22-26 April 2007, Nagoya, Japan

Simulation Of Rosa-V Test 6.2 Using Trace V.4.274 Code
A. Jasiulevicius, O. Zerkak, Juan. Macian,
Icone-15, 22-26 April 2007, Nagoya, Japan

Assessment Of Trace Film Condensation Models With And Without Non-Condensable Gases
A. Manera, Juan. Macian,
Nureth-12, 30 September - 4 October 2007, Pittsburgh, Usa

Lwr Multi-Physics Developments And Applications Within The Framework Of The Nuresim Europen Project
O. Zerkak, P. Coddington, N. Crouzet, E. Rover, J. Jimenez, D. Cuervo
Proc. Int. Top.Meetg. On Mathematics &Computation And Supercomputing in Nuclear Applications, M&C+Sna 2007, 15-19 April 2007, Monterey, Usa

Stability Effect Of The Lateral Lift Force In Homogeneous Bubbly Flow
D. Lucas, E. Krepper, H. Prasser, Manera. M,
Proc. Icmf2007, 9-13 July 2007, Leipzig, Germany

Comparison Between Wire-Mesh Sensor And Conductive Needle-Probes For Measurement Of Interfacial Area Densities
A. Manera, S. Paranjape, B. Ozar, M. Ishii, Hm. Prasser
Proc. Icone-15, 22-26 April 2007, Nagoya, Japan

Investigations On Mixing Phenomena In Single-Phase Flows In A T-Junction Geometry
R. Zboray, A. Manera, B. Niceno, Hm. Prasser
Proc. Nureth-12, 30 September - 4 October 2007, Pittsburgh, Usa, Cd-Rom

Overview of SARNET Deployment and Progress
T. Albiol, T.J. Haste, J.-P. van Dorsselaere, C. Journeau, L. Meyer, B. Chaumont, B.R. Sehgal, B. Schwinges, D. Beraha, A. Annunziato, R. Zeyen
2^nd ERMSAR, Karlsruhe, Germany

Separate-Effect Tests on Zirconium Cladding Degradation in Air Ingress Situations
C. Duriez, M. Steinbrück, D. Ohai, T. Meleg, J.C. Birchley, T.J. Haste
2^nd ERMSAR, Karlsruhe, Germany

Preliminary analyses of the Phebus FPT3 Experiment Using Severe Accident Codes (ATHLET-CD, ICARE/CATHARE, MELCOR)
G. Repetto, O. De Luze, J.C. Birchley, T. Drath, T. Hollands, M.K. Koch, C. Bals, K. Trambauer, H. Austregesilo
2^nd ERMSAR, Karlsruhe, Germany

Achievements and Status of Research Activities in the Source Term Area
T.J. Haste, J. Giordano, L.E. Herranz
2^nd ERMSAR, Karlsruhe, Germany

MELCOR Analysis of Loss of Residual Heat Removal during Mid-Loop Operation in a Westinghouse Two-Loop PWR
J.C. Birchley, T.J. Haste, M. Richner
ICAPP, Nice, France

Characterization of TiO2 agglomerates for the investigation of aerosol behavior in a steam generator tube rupture event
T.M. Lind, S. Danner, D.J. Suckow, S. Güntay, U. Trapper, A. Auvinen
ICAPP, Nice, France

MELCOR and SCDAP Analyses of Loss-of-Coolant Accidents During Cooldown in a Westinghouse 2-Loop PWR
T.J. Haste, J.C. Birchley, M. Richner
16^th NENE Conference, Portoroz, Slovenia
http://www.nss.si/proc/port2007/htm/pdf/210.pdf

Variable Property Effects on Vapor Condensation with a noncondensable Gas
Y. Liao, K. Vierow
12^th NURETH Conference, Pittsburgh, USA

Simulations Of The Halden Ifa-650.3/.4 High Burnup Loca Test With Trace And Falcon: A Preliminary Study On Axial Relocation
Y. Aounallah, G. Khvostov, A. Romano, H. Wallin, M. Zimmermann, Kolstad. A, Ek. E, Kekkonen. M,
Int. Meeting On Lwr Fuel Performance (**Topfuel 2006), 22-26 October 2006, Salamanca, Spain

Analysis Of Umsicht Water Hammer Benchmark Tests: Results From Psi Using Trace And Relap5 Codes
W. Barten, A. Jasiulevicius, O. Zerkak, Juan. Macian,
7th Int. Conference On Hydroinformatics (Hic 2006), 4-8 September 2006, Nice, France, Vol. Ii, 1227-1234, 2006

Investigation Of Heat Transfer Mechanismus Under Shutdown Plant Conditions With Tracev4. 160
A. Jasiulevicius, O. Zerkak, Juan. Macian,
Int. Congress On Advances in Nuclear Power Plants (Icapp'06), 4-8 June 2006, Reno, USA, 1820-1828, 2006

Impact Of Different Correlation On Tracev4.160 Predicted Critical Heat Flux
A. Jasiulevicius, Juan. Macian,
Int. Congress On Advances in Nuclear Power Plants (Icapp'06), 4-8 June 2006, Reno, USA, 1820-1828, 2006

Predictions Of Critical Heat Flux In Annular Pipes With Tracev4.160 Code
A. Jasiulevicius, Juan. Macian,
14th Int. Conference On Nuclear Engineering (Icone14),17-20 July 2006, Miami, USA, 2006

Steady-State Film Boiling Heat Transfer Simulated With Tracev4.160
A. Jasiulevicius, Juan. Macian,
14th Int. Conference On Nuclear Engineering (Icone14),17-20 July 2006, Miami, USA, 2006

Assessment Of Standard Point-Wise Neutron Data Libraries For Criticality Safety Analysis With A Monte Carlo Code
E. Kolbe, A. Vasiliev, M. Zimmermann,
Proc. Physor-2006, 10-14 September 2006, Vancouver, Canada, 2006

CASMO-4/SIMULATE-3/MCNPX Analysis Of A Reactor Pressure Vessel Scraping Test
A. Vasiliev, H. Ferroukhi, M. Zimmermann,
Proc. Physor-2006, 10-14 September 2006, Vancouver, Canada, 2006

A Methodology For The Quantification Of Uncertainty In Best Estimate Code Physical Models
P. Vinai, Juan. Macian, Chawla. R,
Int. Congress On Advances in Nuclear Power Plants (Icapp'06), 4-8 June 2006, Reno, Usa, 1087-1098, 2006

Assessment of a new Fluent Model for Particle Dispersion in Turbulent Flows
A. Dehbi
1^st CFD4NRS, Garching, Germany

MELCOR Simulation of the TMI-2 Severe Accident and Initial Recovery Phases
T.J. Haste, J.C. Birchley, E. Cazzoli, J. Vitazkova
ICAPP, Reno, USA

SARNET: Integrating Severe Accident Research in Europe - Safety Issues in the Source Term Area
T.J. Haste, P. Giordano, L.E. Herranz, J.-C. Micaelli
ICAPP, Reno, USA

Pre-test Analytical Support for Experiments QUENCH-10, -11 and -12
J.C. Birchley, T.J. Haste, W. Hering, C. Homann
15^th NENE Conference, Portoroz, Slovenia
http://www.nss.si/proc/port2006/pdf/0812.pdf

Mechanical Modeling Of Pressure Tube Tests Using The Feat Code
W. Barten, A. Hermann, H. Wallin
Jahrestagung Kerntechnik 2005, 10-12 May 2005, Nuremberg, Germany, 2005

Assessment Of A BWR Analytical Reduced Order Model Against The System Code Ramona: Applicability And Limitations
A. Dokhane, D. Hennig, Uddin. Rizwan, R. Chawla
Proc. 13th Int. Conference On Nuclear Engineering (Icone13), 16-20 May 2005, Beijing, China, 2005

A Reactor Noise Analysis Methodology For Bwr Core Stability Evaluation: Application And Assessment To Leibstadt Stability Tests
A. Dokhane, H. Ferroukhi, M. Zimmermann, Aguirre. A,
Int. **Topical Meeting On Mathematics And Computation (M&C 2005), 12-15 September 2005, Avignon, France, 2005

Evaluation Of The PWR Rea Pulse Width For Realistic Uo2/Mox Cores
H. Ferroukhi, M. Zimmermann,
Int. **Topical Meeting On Mathematics And Computation (M&C 2005), 12-15 September 2005, Avignon, France, 2005

Assessment Of Trace Code Against CHF Experiments
A. Jasiulevicius, Juan. Macian, Coddington. R, Sanchez. P,
Proc. 11th Int. **Topical Meeting On Nuclear Reactor Thermal Hydraulics (Nureth-11), 2-6 October 2005, Avignon, France, 2005

Loss Of Residual Heat Removal System: Simulation By Tracev4.00 Simulation Of A PKL Experiment
A. Jasiulevicius, O. Zerkak, Juan. Macian,
Trans.Am.Nuc.Soc., Volume 92, Pp 442-443, June 2005

CHF Experiments In Single Tubes Tracev4.050 Code Validation
A. Jasiulevicius, Juan. Macian,
Trans.Am.Nuc.Soc., Volume 92, Pp 430-432, June 2005

Effect Of The Power Pulse Shape On The Fuel Thermal-Mechanical Response To Rias: A Study Using Falcon And Scanair
A. Romano, M. Zimmermann,
Proc. Water Reactor Fuel Performance Meeting, WRFPMO5, 2-6 October 2005, Kyoto, Japan, 2005

Analysis Of MCNPX/JEF-2.2 And JENDL-3.3 Results For A Suite Of The Low-Enriched Thermal Compound Uranium Benchmarks
A. Vasiliev, J. Lebenhaft, M. Zimmermann,
Int. **Topical Meeting On Mathematics And Computation (M&C 2005), 12-15 September 2005, Avignon, France, 2005

Optimization Of Uo2 Fueled PWR Core Design
E. Greenspan, F. Ganda, Z. Shayer, N. Todreas, J. Malen, C. Shuffler, J. Trant, A. Romano, B. Petrovic, H. Garkish
Proc. Int. Congress On Advances in Nuclear Power Plants, 15-19 May 2005, Seoul, Korea, 2005

Overwiev of SARNET Deployement and Progress
J.C. Micaelli, T.J. Haste, J.-P. van Dorsselaere, J.-M. Bonnet, L. Meyer, B. Chaumont, D. Beraha, A. Annunziato, B.R. Sehgal, K. Trambauer, B. Adroguer
1^st ERMSAR, Aix en Provence, France

Core Reflooding: Synthesis of the QUENCH Program and its Impact on Code Modelling
M. Steinbrück, W. Hering, J. Stuckert, J.C. Birchley, E. Brunet-Thibault, T. Drath, N. Seiler, K. Trambauer, M.S. Veshchunov
1^st ERMSAR, Aix en Provence, France

Overview of SARNET Activities in the Source Term Area
T.J. Haste, P. Giordano, L.E. Herranz
1^st ERMSAR, Aix en Provence, France

Aerosol Behaviour in SGTR accidents
S. Güntay, L.E. Herranz, V. Layly, T. Routamo, A. Auvinen
1^st ERMSAR, Aix en Provence, France

Progress in Modelling Silver-Indium-Cadmium Control Rod Degradation and Release
B. Maliverney, K. Trambauer, W. Plumecocq, R. Dubourg, T.J. Haste
1^st ERMSAR, Aix en Provence, France

Session 8 - General Discussion - Conclusions and Recommendations
B. Adroguer, J.-M. Bonnet, B. Chaumont, M. Hugon, T.J. Haste, L. Meyer, J.-C. Micaelli, B.R. Sehgal, K. Trambauer, J.-P. van Dorsselaere
1^st ERMSAR, Aix en Provence, France

Summary of SARNET Activities in the Source Term Area
T.J. Haste, P. Giordano, L.E. Herranz
1^st ERMSAR, Aix en Provence, France

SARNET: Severe Accident Research Network Key Issues in the Area of Source Term
P. Giordano, T.J. Haste, L.E. Herranz, J.C. Micaelli
14^th NENE Conference
http://www.nss.si/proc/bled2005/htm/pdf/00040.pdf

CFD Simulation of Particle Depletion Inside a Large Volume with Prevailing Natural Circulation
A. Dehbi
11^th NURETH Conference

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2001 - 2004

Boilling Suppression In Convective Flow
Y. Aounallah
Proc. Icapp04, 13-17 June 2004, Pittsburgh, USA

Retran-3d Analysis Of The Extreme Cases Of Phase 3 Of The Peach Bottom 2 Turbine Trip Benchmark
W. Barten, P. Coddington
Jahrestagung Kerntechnik, 25-27 May 2004, DüSseldorf, Germany, Vol. Tagungsband, 3-8, 2004

Bifurcation Analysis Using The System Code Ramona
A. Dokhane, D. Hennig, Uddin. Rizwan, R. Chawla
Proc. 12th Int. Conference On Nuclear Engineering (Icone 12), 25-29 April 2004, Arlington, USA, 2004

Uncertainty Analysis Applied To Fuel Depletion Calculations
Macian-Juan R., Zimmermann M.A., Chawla R..
Physor 2004, 25-29 April 2004, Chicago, USA, 2004

Assessment Of Casmo-4 Predictions Of The Iso**Topic Inventory Of High Burn-Up Mox Fuel
Macian-Juan R., Zimmermann M.A., Chawla R..
Physor 2004, 25-29 April 2004, Chicago, USA, 2004

Level-Swell Prediction With Retran-3d And Its Application To A Bwr Steam Line Break Analysis
Y. Aounallah, K. Hofer
Proc. Int. Congress On Advanced Nuclear Power Plants (Icapp'03), 4-7 May 2003, CóRdoba, Spain

Peach Bottom Bwr Turbine Trip Benchmark Phase 3: Analysis Of Full Plant System With 3d-Neutronics Using Retran-3d
W. Barten, P. Coddington
Proc. Mathematics & Computations 2003, 6-10 April 2003, Gatlinburg, Tennessee, USA

Validation Of Monteburns For Mox Fuel Using Ariane Experimental Results
J.R. Lebenhaft, H.R. Trellue
Proc. Mathematics & Computations 2003, 6-10 April 2003, Gatlinburg, Tennessee, USA

Nuclear-Coupled Thermal-Hydraulic Nonlinear Stability Analysis Using A Novel Bwr Reduced Order Model: Part 1 - The Effects Of Using Drift Flux Versus Homogeneous Equilibrium Models
A. Dokhane, D. Hennig, R. Chawla, Rizwan-Uddin
Proc. Icone11, 20-23 April 2003, Tokyo, Japan

Nuclear-Coupled Thermal-Hydraulic Nonlinear Stability Analysis Using A Novel Bwr Reduced Order Model: Part 2 - Stability Limits Of In-Phase And Out-Of-Phase Modes
A. Dokhane, D. Hennig, R. Chawla, Rizwan-Uddin
Proc. Icone11, 20-23 April 2003, Tokyo, Japan

Thematic Network for a PHEBUS FPT-1 International Standard Problem (THENPHEBISP)
B. Clément, T.J. Haste, E. Krausmann, S. Dickinson, G. Gyenes, J. Duspiva, F. de Rosa, S. Paci, F. Martin-Fuertes, W. Scholytssek, H.J. Allelein, S. Güntay, B. Arien, S. Marguet, M. Leskovar, A. Sartmadjiev
FISA 2003 Symposium on EU Research in Reactor Savety

Validation of Severe Accident Codesagainst PHEBUS FP for Plant Applications (PHEBEN2)
K. Müller, S. Dickinson, C. de Pascale, N. Hanniet, L.E. Herranz, F. de Rosa, G. Henneges, J. Langhans, C. Housiadas, V. Wichers, J.C. Birchley, S. Paci, F. Martin-Fuertes
FISA 2003 Symposium on EU Research in Reactor Savety

Iodine Chemistry and Mitigation Mechanisms (ICHEMM)
S. Dickinson, H.E. Sims, F. Funke, S. Güntay, H. Bruchertseifer, J.O. Liljenzin, H. Glänneskog, M.P. Kissane, L. Cantrel, E. Krausmann, A. Rýdl
FISA 2003 Symposium on EU Research in Reactor Savety

European Expert Network for the Reduction of Uncertainties in Severe Accident Safety Issues (EURSAFE)
D. Magallon, A. Mailiat, J.M. Seiler, K. Atkhen, H. Sjövall, S. Dickinson, J. Jakab, L. Meyer, M. Buerger, K. Trambauer, L. Fickert, B.R. Sehgal, Z. Hózer, J. Bagués, F. Martin-Fuertes, R. Zeyen, M. El-Shanawany, S. Güntay, C. Tinkler
FISA 2003 Symposium on EU Research in Reactor Savety

Steam Generator Tube Rupture Scenarios (SGTR)
J. Jokiniemi, A. Lähde, A. Auvinen, H. Tuomisto, T. Routamo, P. Lundström, J. Dienstbier, S. Güntay, D.J. Suckow, A. Dehbi, M. Slootman, L.E. Herranz, V. Peyres, J. Polo
FISA 2003 Symposium on EU Research in Reactor Savety

Core Loss during a Severe Accident (COLOSS)
B. Adroguer, J.-P. van Dorsselaere, P. Chatelard, N. Cocuaud, F. Bertrand, L. Bellenfant, D. Bottomley, D. Knoche, V. Vrtilkova, K. Müller, G. Schanz, A. Miassoedov, M. Steinbrück, J. Stuckert, W. Krauss, W. Hering, C. Homann, Z. Hózer, G. Bandini, J.C. Birchley, I. Kleinhietpass, M. Buck, F. Benitez, E. Virtanen, S. Marguet, G. Azarian, H. Plank, A. Berdyshev, M. Veshchunov, V. Kobzar, Y. Zvonarev, A. Goryachev
FISA 2003 Symposium on EU Research in Reactor Savety

Peach Bottom Bwr Turbine Trip Benchmark: Psi Analysis Of Exercise 1 Using Retran-3d
W. Barten, P. Coddington, H. Ferroukhi
Proc. Physor 2002, 7-10 October 2002, Seoul, Korea

Stability And Bifurcation Analyses Of Two-Phase Flow Using A Drift Flux Model And Bifurcation Code Bifdd
A. Dokhane, D. Hennig, Uddin. Rizwan, R. Chawla
Proc. Tenth Int. Conference On Nuclear Engineering (Icone-10), 14-18 April 2002, Arlington, Virginia, Usa

A Parametric Study Of Heated Channels With Two-Phase Flow Using Bifurcation Analysis
A. Dokhane, D. Hennig, Uddin. Rizwan, R. Chawla
Proc. American Nuclear Society Annual Meeting, June 9-13, 2002, Florida, Usa, Trans. Ans, Vol. 86, 131-133 (2002)

Nonlinear Stability Analysis With A Novel BWR Reduced Order Model
A. Dokhane, D. Hennig, Uddin. Rizwan, R. Chawla
Proc. Physor 2002, 7-10 October 2002, Seoul, Korea

Transient 3-D Neutron Kinetic Analysis With Coretran Of A Core Thermal-Hydraulic Boundary Condition Model - Peach Bottom 2 Turbine Trip Benchmark Phase 2
H. Ferroukhi, W. Barten, P. Coddington
Proc. Physor 2002, 7-10 October 2002, Seoul, Korea

ARTIST: An International Project Investigating Aerosol Retention in a Ruptured Steam Generator
S. Güntay, A. Dehbi, D.J. Suckow, J.C. Birchley
ICAPP, Hollywood

ARTIST: a multinational experimental project to investigate fission product retention in a ruptured steam generator
S. Güntay, A. Dehbi, D.J. Suckow, J.C. Birchley
Annual Meeting on Nuclear Technology 2002

The PSI ARTIST project: aerosol retention and accident management issues following a steam generator tube rupture
S. Güntay, A. Dehbi, D.J. Suckow, J.C. Birchley
10^th ICONE Conference
http://dx.doi.org/10.1115/ICONE10-22048

Analysis And Sensitivity Studies With Coretran And Retran-3d Of The Neacrp Rod Ejection Benchmark
H. Ferroukhi, P. Coddington
Proc. Icone-9, Nice France, April 8-12, 2001.

Development Of A Model For Retran-3d For Pressure Losses At T-Junctions
W. Barten, P. Coddington, J. Sullivan
Proc. Icone-9, Nice France, April 8-12, 2001.

Analysis Of Different Hypothetical Recirculation Line Sb-Locas In KKM By Trac-Bf1/V98.1
G. Analytis, Coddington. Th,
Proc. Icone-9, Nice France, April 8-12, 2001.

Best Estimate Analysis Of The Thermal Expansion Scenario During Shutdown In A PWR
R. Macian, L. Nechvatal
Proc. Icone-9, Nice France, April 8-12, 2001.

Coretran/Vipre Assembly Critical Power Assessment Against Nupec BWR Experiments
Y. Aounallah
Proc. Icone-9, Nice, France, April 8-12, 2001.

Retran-3d Results And One-Dimensional Analytical Model For The Critical Power Of A Rod Bundle With Cosine-Shape Heating
W. Barten
Proc. Jahrestagung Kerntechnik 2001, Dresden, Germany, May 15-17, 2001.

Uncontrolled Rod Bank Withdrawal Benchmark Analysis With Coretran And Retran-3d
H. Ferroukhi, P. Coddington
Proc. Ans Int. Meeting On Mathematical Methods For Nuclear Applications, Mc-2001, Salt Lake City, September 2001.

Limited Burnup Credit For Increased Fuel Enrichments In A Swiss PWRStorage Pool
J-M. Parratte, P. Grimm
Proc. Ans **Topical Meeting On Practical Implementation of Nuclear Criticality Safety, Ncsd, Reno, Nevada, Usa, November 11-15, 2001

Some Remarks To Time Series Analysis For BWR Stability Analysis
B. Askari, K. Behringer, D. Hennig
Proc. Ans Int. Meeting On Mathematical Methods For Nuclear Applications, Mc-2001, Salt Lake City, September 2001.

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2000 and before

Assessment Of Retran-3d Against Experimental Loss Of Coolant Scenarios
R. Macian, P. Coddington
Proc. Icone-8, Baltimore, Md, USA 2000.

Assessment Of Retran-3d And Vipre-02 Void Predictions Against Experimental Data
R. Macian, Y. Aounallah, P. Coddington P. Stangroom
Proc. Icone-8, Baltimore, Md, USA 2000.

Towards A Best-Estimate Approach To A Steady-State And Transient Analysis Using The Coretran Code
H. Ferroukhi, P. Coddington, F. Holzgrewe
Proc. Int. Meeting On Best-Estimate Methods in Nuclear Installation Safety Analysis, Washington, Dc, USA, Nov. 2000

Development And Assessment Of Trac-Bf1 For Bwr Loca Applications
G. Th Analytis, P. Coddington
Proc. Int. Meeting On Best-Estimate Methods in Nuclear Installation Safety Analysis, Washington, Dc, USA, Nov. 2000

Validation Of Casmo-4 Against Sims Measured Spatial Nuclide Distributions Inside A 9 Wt% Gd BWR Pin
F. Holzgrewe, Et Al.
Proc. Int. **Topical Meeting On Light Water Reactor Fuel Performance, Park City, Ut, USA, April 2000.

Current And Future Applications Of Thermal-Hydraulic And Neutronic Best-Estimate Methods In Support Of The Swiss Licensing Process
M. A. Zimmermann, W. Van Doesburg
Proc. Csni/Oecd Workshop On Advanced Thermal-Hydraulic And Neutronic Codes: Current And Future Applications, Barcelona, Spain, April 10-13, 2000.

A Study Of The Performance Of Void Fraction Correlations Used In The Context Of Drift-Flux Two-Phase Flow Models
P. Coddington, R. Macian
Proc. Int. Meeting On Trends in Numerical And Physical Modelling For Industrial Multiphase Flows , Cargese, Corsica, September 27-29, 2000.

Remarks On Regional Power Oscillations In BWRs
D. Ginestar, D. Hennig, R. Miro, G. Verdu
Proc. Int. Conference On Mathematics And Computation, Reactor Physics And Environmental Analysis in Nuclear Applications, Madrid, Spain, Sept 27-30, 1999

Implementation Of An Improved Interfacial Mass And Energy Transfer Model In Retran- 3d
R. Macian, P. Cebull, P. Coddington, M. Paulsen
Proc. 9th Int. Meeting On Nuclear Reactor Thermal Hydraulics, Oct 4-8, 1999, San Francisco, Ca

Vipre-02 Subchannel Validation Against Nupec Void Fraction Data
Y. Aounallah, P. Coddington
Proc. 9th Int. Meeeting On Nuclear Reactor Thermal Hydraulics, Oct 4-8, 1999, San Francisco, Ca

Analysis Of Rod Bundle And Subchannel, Subcooled Boiling Experiments Using Retran-3d, Trac-Bf1 And Vipre-02
P. Coddington, Y. Aounallah, D. Maier, D. Reedha
Proc. 9th Int. Meeting On Nuclear Reactor Thermal Hydraulics, Oct 4-8, 1999, San Francisco, Ca

The Physical Mechanism Of Core-Wide And Local Instabilities At The Forsmark-1 BWR
G. Th. Analytis, D. Hennig, J. K-H. Karlsson
Proc. 9th Int. Meeting On Nuclear Reactor Thermal Hydraulics, Oct 4-8, 1999, San Francisco, Ca

Drain Lain Melt Through Experiment Under Water-free Conditions
K. Nakada, B.S. Jäckel, H. Hirschmann, J.A. Patorski, G. Duijvestijn
7^th ICONE Conference

Assessment Of The Slip Options In Retran-3d Against A Wide Range Of Rod Bundle Void Data
D. Maier, P. Coddington
Proc. Icone6, 6th Int. Conference On Nuclear Engineering, May 10-15, 1998, San Diego, California, Usa

Einige Bemerkungen Zum Physikalischen Mechanismus Der Entstehung Von Oszillatorischen Instabilitäten In Siedewasserreaktoren
D. Hennig
Proc. Jahrestagung Kerntechnik Mai 1998, MüNchen.

Evaluation Of The Slip Options In Retran-3d
D. Maier, P. Coddington
Proc. 9th Int. Retran Meeting, June 7-10, 1998, Monterey, Ca, USA

Vipre-02 Subchannel Validation Against Nupec Bwr Void Fraction Data
Y. Aounallah, P. Coddington
Proc. 9th Int. Retran Meeting, June 7-10, 1998, Monterey, Ca, USA

Implementation Of An Improved Interfacial Mass And Energy Transfer Model In Retran-3d
R. Macian, P. Cebull, P. Coddington, M. Paulsen
Proc. 9th Int. Retran Meeting, June 7-10, 1998, Monterey, Ca, USA

Bwr Stability Analysis At PSI
D. Hennig
Proc. Int. Conference On The Physics of Nuclear Science And Technology, Oct. 5 - 8, 1998, Long Island, New York

Behavior of a passive heat removal system following a severe accident
A. Dehbi, D.J. Suckow, S. Güntay
Annual Meeting on Nuclear Technology

Evaluation Of The Trac-Bf1 Code Against BWR/6 Start-Up Tests
B. Brodbeck, P. Coddington
Proc. Icone5, Nice France, May 26-30, 1997, Paper No. 2461.

Review Of Wide Range Void Correlations Against An Extensive Database Of Rod Bundle Void Measurements
D. Maier, P. Coddington
Proc. Icone5, Nice, France, May 26-30, 1997, Paper No. 2434.

Containment behaviour in the event of core melt with gaseous and aerosol releases (CONGA)
E. Friesen, S. Güntay, J. Lopez Jimenez, G.F. de Santi, M. Valisi
FISA-97 Symposium on EU Research on Severe Accidents

ESBWR passive aerosol removal - Maintaining plant simplicity for offsite dose reduction
S. Güntay, D.J. Suckow, N.B. Siccama, S.S. Khorana
Economic Nuclear Power for the 21st Century

Further Assessment of the Chemical Modelling of Iodine in IMPAIR 3 Code using ACE/RTF Data
R.C. Cripps, S. Güntay
4^th CSNI Workshop on the Chemistry of Iodine in Reactor Safety

Primary Circuit Iodine Model Addition to IMPAIR-3
D.J. Osetek, D.L.Y. Louie, S. Güntay, R.C. Cripps
4^th CSNI Workshop on the Chemistry of Iodine in Reactor Safety

Experimental Investigations of Mixed Convection
D.J. Suckow, U. Müller, L. Krebs
Proceedings of the 10^th International Heat Transfer Conference

Simulation of pool scrubbing experiments using BUSCA
A. Dehbi, S. Güntay
3^rd International Conference on Containment Design and Operation

Model of condensation in stagnant steam-noncondensable gas mixtures
A. Dehbi, M.W. Golay, M.S. Kazimi
Transactions of the American Nuclear Society

The transferability to reactor conditions of thermo-hydraulics model investigations of decay heat removal
D. Weinberg, D.J. Suckow, U. Müller, H. Hoffmann
Proceedings of the 1990 International Fast Reactor Safety Meeting

Theoretical investigations on thermal behaviour of nuclear fuel and NEPTUN heater element
S.N. Aksan, S. Güntay, V. Varadi
Transactions of the American Nuclear Society

Sensitivity Analysis of PWR and HGTR Fuel Cycle Costs
S. Güntay
Transactions of the American Nuclear Society

Sensitivity Analysis of PWR and HGTR Fuel Cycle Costs
S. Güntay
Transactions of the American Nuclear Society

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