Journal publications of the Laboratory for Reactor Physics and Thermal-Hydraulics

Our scientists, post docs and students regularly publish articles in scientific magazines primarily in the nuclear engineering and technical field. For this purpose, each submitted article is first thoroughly reviewed and then approved.

Here you will find a selection of journals that regularly publish articles from our laboratory:

2024

Al-Yahia OS, Clifford I, Ferroukhi H
Assessment of TRACE code for modeling of passive safety system during long transient SBO via PKL/SACO facility
Nuclear Engineering and Technology. 2024; 56(8): 2893-2905. https://doi.org/10.1016/j.net.2024.02.050
DORA PSI
Al-Yahia OS, Bernard M, Clifford I, Perret G, Bajorek S, Ferroukhi H
The influence of droplet breakup model on the prediction of reactor core parameters during reflood conditions
Nuclear Engineering and Design. 2024; 416: 112815 (16 pp.). https://doi.org/10.1016/j.nucengdes.2023.112815
DORA PSI
Albà A, Adelmann A, Münster L, Rochman D, Boiger R
Fast uncertainty quantification of spent nuclear fuel with neural networks
Annals of Nuclear Energy. 2024; 196: 110204 (8 pp.). https://doi.org/10.1016/j.anucene.2023.110204
DORA PSI
Alcayne V, Cano-Ott D, Garcia J, González-Romero E, Martínez T, Rada AP, et al.
A segmented total energy detector (sTED) optimized for (n, γ) cross-section measurements at n_TOF EAR2
Radiation Physics and Chemistry. 2024; 217: 111525 (11 pp.). https://doi.org/10.1016/j.radphyschem.2024.111525
DORA PSI
Alhassan E, Rochman D, Schnabel G, Koning AJ
Bayesian model averaging (BMA) for nuclear data evaluation
Nuclear Science and Techniques. 2024; 35(11): 205 (26 pp.). https://doi.org/10.1007/s41365-024-01543-w
DORA PSI
Amaducci S, Colonna N, Cosentino L, Cristallo S, Finocchiaro P, Krtička M, et al.
Measurement of the Ce 140 (n,γ) cross section at n_TOF and its astrophysical implications for the chemical evolution of the universe
Physical Review Letters. 2024; 132(12): 122701 (8 pp.). https://doi.org/10.1103/PhysRevLett.132.122701
DORA PSI
Ambrožič K, Knospe A, Pakari O, Hübner S, Hursin M, Lange C, et al.
CORTEX experiments, Part II: Postprocessing of neutron noise time series to determine reliable mean and uncertainties
Annals of Nuclear Energy. 2024; 208: 110704 (16 pp.). https://doi.org/10.1016/j.anucene.2024.110704
DORA PSI
Araujo DM, Auchmann B, Brem A, Daly M, Hug C, Michlmayr T, et al.
Assessment of training performance, degradation and robustness of paraffin-wax impregnated Nb₃Sn demonstrator under high magnetic field
IEEE Transactions on Applied Superconductivity. 2024; 34(5): 7000208 (8 pp.). https://doi.org/10.1109/TASC.2024.3368995
DORA PSI
Arumugam VK, Mantzaras J, Gantenbein A, Doll U, Schildhauer T
Experimental and numerical investigation of high-pressure methane catalytic synthesis from H₂ and CO₂
Proceedings of the Combustion Institute. 2024; 40(1-4): 105206 (7 pp.). https://doi.org/10.1016/j.proci.2024.105206
DORA PSI
Baccou J, Glantz T, Ghione A, Sargentini L, Fillion P, Damblin G, et al.
A systematic approach for the adequacy analysis of a set of experimental databases: Application in the framework of the ATRIUM activity
Nuclear Engineering and Design. 2024; 421: 113035 (16 pp.). https://doi.org/10.1016/j.nucengdes.2024.113035
DORA PSI
Baek S-I, Chae M-S, Chung B-J
Numerical investigation on flow characteristics and heat transfer of mixed convection in a packed bed
International Communications in Heat and Mass Transfer. 2024; 159(Part A): 107994 (12 pp.). https://doi.org/10.1016/j.icheatmasstransfer.2024.107994
DORA PSI
Balibrea-Correa J, Lerendegui-Marco J, Babiano-Suarez V, Domingo-Pardo C, Ladarescu I, Tarifeño-Saldivia A, et al.
Pushing the high count rate limits of scintillation detectors for challenging neutron-capture experiments
Nuclear Instruments and Methods in Physics Research, Section A: Accelerators, Spectrometers, Detectors and Associated Equipment. 2024; 1064: 169385 (13 pp.). https://doi.org/10.1016/j.nima.2024.169385
DORA PSI
Berry L, Vasiliev A, Hursin M, Rochman D, Frankl M, Ferroukhi H
Towards establishment of an efficient approach for validation of PWR full core Monte Carlo simulations at hot zero power conditions
Progress in Nuclear Energy. 2024; 172: 105203 (16 pp.). https://doi.org/10.1016/j.pnucene.2024.105203
DORA PSI
Bersano A, Lombardo C, Alblouwy F, Karppinen I, Silde A, Nikitin K, et al.
Benchmark exercise on ELSMOR passive heat removal system
Nuclear Engineering and Design. 2024; 419: 112961 (14 pp.). https://doi.org/10.1016/j.nucengdes.2024.112961
DORA PSI
Brem A, Duda M, Müller C, Garcia H, Hug C, Daly M, et al.
From hot to cold: advanced materials and processes for Nb₃Sn based magnets
IEEE Transactions on Applied Superconductivity. 2024; 34(5): 7700105 (5 pp.). https://doi.org/10.1109/TASC.2023.3338588
DORA PSI
Chae MS, Kelm S, Paladino D
Analyses of International Standard Problem ISP-47 TOSQAN experiment with containmentFOAM
Nuclear Engineering and Technology. 2024; 56(2): 611-623. https://doi.org/10.1016/j.net.2023.10.038
DORA PSI
Chae MS, Lee J, Cho HK, Kelm S, Paladino D
Analyses of jet buoyant flow in a multicompartment containment using an open-source solver
Nuclear Technology. 2024. https://doi.org/10.1080/00295450.2024.2362527
DORA PSI
Cherezov A, Vasiliev A, Ferroukhi H
Low precision preconditioning for solving neutron diffusion eigenvalue problem by finite element method
Annals of Nuclear Energy. 2024; 206: 110575 (11 pp.). https://doi.org/10.1016/j.anucene.2024.110575
DORA PSI
Coppo Leite V, Merzari E, Mao J, Petrov V, Manera A
High-fidelity simulation of mixing phenomena in large enclosures
Nuclear Science and Engineering. 2024; 198(7): 1386-1403. https://doi.org/10.1080/00295639.2023.2186159
DORA PSI
Darby FB, Pakari OV, Hua MY, Lamirand V, Clarke SD, Pautz A, et al.
Neutron-gamma noise measurements in a zero-power reactor using organic scintillators
IEEE Transactions on Nuclear Science. 2024; 71(5): 1033-1040. https://doi.org/10.1109/TNS.2023.3337657
DORA PSI
Dehbi A, Kapulla R
CFD simulations of helium layer erosion in one PANDA vessel following cooler activation
Nuclear Engineering and Design. 2024; 422: 113154 (14 pp.). https://doi.org/10.1016/j.nucengdes.2024.113154
DORA PSI
Dokhane A, Vasiliev A, Ferroukhi H
Stability and bifurcation analysis of Oskarshamn-2 event with nuclear data and kinetic parameter uncertainties
Nuclear Engineering and Design. 2024; 430: 113678 (11 pp.). https://doi.org/10.1016/j.nucengdes.2024.113678
DORA PSI
Doll U, Kapulla R, Dues M, Steinbock J, Melnikov S, Röhle I, et al.
Towards time-resolved multi-property measurements by filtered Rayleigh scattering: diagnostic approach and verification
Experiments in Fluids. 2024; 65(1): 2 (13 pp.). https://doi.org/10.1007/s00348-023-03740-6
DORA PSI
D’Ambrosi V, Sercombe J, Bejaoui S, Chaieb A, Baurens B, Largenton R, et al.
P2M simulation exercise on past fuel melting irradiation experiments
Nuclear Technology. 2024; 210(2): 189-2015. https://doi.org/10.1080/00295450.2023.2194270
DORA PSI
Fagnoni F, Kursun E．C, Busi M, Konarski P, Yetik O, Spolenak R, et al.
Hydrogen enhanced localized plasticity in zirconium as observed by digital image correlation
Journal of Nuclear Materials. 2024; 590: 154873 (10 pp.). https://doi.org/10.1016/j.jnucmat.2023.154873
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
Journal of Engineering for Gas Turbines and Power. 2024; 146(2): 021012 (8 pp.). https://doi.org/10.1115/1.4063524
DORA PSI
Fogliatto E, Clifford I
Assessment of wall models for coarse-mesh RANS simulations
Annals of Nuclear Energy. 2024; 209: 110807 (15 pp.). https://doi.org/10.1016/j.anucene.2024.110807
DORA PSI
Grasso M, Petrov V, Manera A
Accuracy and error analysis of optical liquid film thickness measurement with total internal reflection method (TIRM)
Experiments in Fluids. 2024; 65(6): 83 (17 pp.). https://doi.org/10.1007/s00348-024-03820-1
DORA PSI
Huang P-H, Ahn T, Manera A, Petrov V
Investigation of key parameters for the operation of a sodium heat pipe with visualization using X-ray radiography
Applied Thermal Engineering. 2024; 236: 121867 (12 pp.). https://doi.org/10.1016/j.applthermaleng.2023.121867
DORA PSI
Hursin M, Vasiliev A, Rochman D, Dokhane A, Ferroukhi H
Monte Carlo analysis of BWR geometries using a cycle check-up methodology
Annals of Nuclear Energy. 2024; 195: 110170 (17 pp.). https://doi.org/10.1016/j.anucene.2023.110170
DORA PSI
Huxford A, Zou L, Hu R, Petrov V, Manera A
Validation of a hybrid domain overlapping coupling between SAM and CFD against the TALL-3D transients
Nuclear Technology. 2024. https://doi.org/10.1080/00295450.2024.2352665
DORA PSI
Kapulla R, Kelm S, Doll U, Liu X, Paranjape S, Paladino D
Large-scale PANDA facility – radiation experiments and CFD calculations
Kerntechnik. 2024; 89(2): 202-217. https://doi.org/10.1515/kern-2023-0060
DORA PSI
Khvostov G
Interpretation of the online measurement data for selected tests of the RISOE-III project
Journal of Nuclear Materials. 2024; 599: 155219 (17 pp.). https://doi.org/10.1016/j.jnucmat.2024.155219
DORA PSI
Kim T, Doll U, Faldella F, Jansohn P
Quantification of mixing quality effects on flashback limits for H₂-rich fuel gases in lean premixed combustion using laser-induced fluorescence of acetone
Journal of Engineering for Gas Turbines and Power. 2024; 146(7): 071004 (7 pp.). https://doi.org/10.1115/1.4064359
DORA PSI
Konarski P, Cozzo C, Khvostov G, Ferroukhi H
Development and testing of the hydrogen behavior tool for Falcon - HYPE
Nuclear Engineering and Technology. 2024; 56(2): 728-744. https://doi.org/10.1016/j.net.2023.11.012
DORA PSI
Kristian A, Richard H, Pascal V, Braillard O, Manera A, Petrov V
An NEA/OECD benchmark-experiment for the validation of CFD for mixing and thermal fatigue in T-junction dead leg flows
Nuclear Engineering and Design. 2024; 417: 112813 (16 pp.). https://doi.org/10.1016/j.nucengdes.2023.112813
DORA PSI
Ligonnet T, Laureau A, Simbsler P, Pautz A, Lamirand V
Design of an open-loop pile-oscillation program in the CROCUS reactor
IEEE Transactions on Nuclear Science. 2024; 71(5): 1001-1009. https://doi.org/10.1109/TNS.2024.3371183
DORA PSI
Ligonnet T, Laureau A, Pautz A, Lamirand V
High-resolution modeling without computation slowdown for PETALE in CROCUS
Nuclear Science and Engineering. 2024. https://doi.org/10.1080/00295639.2024.2357963
DORA PSI
Malicki M, Darnowski P, Lind T
An iPWR MELCOR 2.2 study on the impact of the modeling parameters on code performance and accident progression
Energies. 2024; 17(13): 3279 (24 pp.). https://doi.org/10.3390/en17133279
DORA PSI
Malicki M, Lind T
MELCOR 2.2 iPWR LOCA type accident analysis, PART I: Thermal-hydraulics
Nuclear Engineering and Design. 2024; 428: 113433 (13 pp.). https://doi.org/10.1016/j.nucengdes.2024.113433
DORA PSI
Malicki M, Lind T
MELCOR 2.2 iPWR LOCA type accident analysis, PART II: BDBA
Nuclear Engineering and Design. 2024; 430: 113667 (15 pp.). https://doi.org/10.1016/j.nucengdes.2024.113667
DORA PSI
Mao J, Che S, Petrov V, Manera A
Benchmark experiments for turbulent mixing in the scaled-down upper plenum of high-temperature gas-cooled reactors under accident scenario
Nuclear Science and Engineering. 2024; 198(7): 1371-1385. https://doi.org/10.1080/00295639.2023.2186726
DORA PSI
Mao J, Manera A, Petrov V
High-resolution experiments for mixing in large enclosures
Nuclear Engineering and Design. 2024; 417: 112828 (11 pp.). https://doi.org/10.1016/j.nucengdes.2023.112828
DORA PSI
Mao J, Vishwakarma V, Welker Z, Tai CK, Bolotnov IA, Petrov V, et al.
Validation of RANS-based turbulence models against high-resolution experiments and DNS for buoyancy-driven flow with stratified fronts
Nuclear Science and Engineering. 2024; 198(7): 1404-1425. https://doi.org/10.1080/00295639.2023.2241800
DORA PSI
Mascari F, Bersano A, Massone M, Agnello G, Coindreau O, Beck S, et al.
Main outcomes of the Phebus FPT1 uncertainty and sensitivity analysis in the EU-MUSA project
Annals of Nuclear Energy. 2024; 196: 110205 (14 pp.). https://doi.org/10.1016/j.anucene.2023.110205
DORA PSI
Nikitin K, Clifford I, Ferroukhi H
Minimal requirements to thermal-hydraulics/3D-neutron kinetics clustering for BWR transient analysis
Annals of Nuclear Energy. 2024; 195: 110147 (12 pp.). https://doi.org/10.1016/j.anucene.2023.110147
DORA PSI
Pakari O, Mager T, Frajtag P, Pautz A, Lamirand V
Gamma noise to non-invasively monitor nuclear research reactors
Scientific Reports. 2024; 14(1): 8409 (10 pp.). https://doi.org/10.1038/s41598-024-59127-y
DORA PSI
Paranjape S, Kapulla R, Kudinov P, Chae MS, Paladino D
Experimental results of thermocline evolution in a water pool under combined effect of steam venting and water injection
Nuclear Engineering and Design. 2024; 419: 112914 (17 pp.). https://doi.org/10.1016/j.nucengdes.2024.112914
DORA PSI
Perkowski J, Alcayne V, Andrzejewski J, Cano-Ott D, Gawlik-Ramięga A, Mendoza E, et al.
Multi-section fission ionization chamber for measurement of ²³⁹ Pu(n,γ) reaction in fission tagging method
Nuclear Instruments and Methods in Physics Research, Section A: Accelerators, Spectrometers, Detectors and Associated Equipment. 2024; 1067: 169649 (2 pp.). https://doi.org/10.1016/j.nima.2024.169649
DORA PSI
Perret G, Clifford ID, Ferroukhi H
Choked-flow model parameter uncertainty determination using hierarchical calibration
Annals of Nuclear Energy. 2024; 207: 110672 (12 pp.). https://doi.org/10.1016/j.anucene.2024.110672
DORA PSI
Ramos Perez A, Lind T, Petrov V, Manera A, Prasser HM
Characterization of turbulent multiphase particle mass transfer in gas-liquid flows
International Journal of Heat and Mass Transfer. 2024; 234: 126044 (16 pp.). https://doi.org/10.1016/j.ijheatmasstransfer.2024.126044
DORA PSI
Ramos Perez A, Lind T, Petrov V, Manera A, Prasser HM
Two-phase hydrodynamics and aerosol mass transfer characterization in pool scrubbing: a simultaneous measurement technique
Journal of Aerosol Science. 2024; 178: 106336 (17 pp.). https://doi.org/10.1016/j.jaerosci.2024.106336
DORA PSI
Reventos F, D'Auria F, Herranz L, Sanchez Perea M, Carlos Alberola S, Freixa J, et al.
What is the future for nuclear fission technology? A technical opinion from the guest editors of VSI NFT series and the editor of the Journal Nuclear Engineering and Design
Nuclear Engineering and Design. 2024; 425: 113332 (11 pp.). https://doi.org/10.1016/j.nucengdes.2024.113332
DORA PSI
Rochman D, Algora A, Àlvarez-Velarde F, Bardelay A, Bremnes Ø, Cabellos O, et al.
An introduction to Spent Nuclear Fuel decay heat for Light Water Reactors: a review from the NEA WPNCS
EPJ Nuclear Sciences and Technologies. 2024; 10: 9. https://doi.org/10.1051/epjn/2024010
DORA PSI
Seo S, Folsom C, Jensen C, Kamerman D, Giaccardi L, Cherubini M, et al.
International fuel performance study of fresh fuel experiments for PCMI effects during RIA experiments
Nuclear Engineering and Design. 2024; 430: 113673 (19 pp.). https://doi.org/10.1016/j.nucengdes.2024.113673
DORA PSI
Seyffert C, Malicki M
Validation methods in modelling the PANDA IPSS experiment: a MELCOR 2.2 assessment of a passive isolation condenser
Progress in Nuclear Energy. 2024; 177: 105430 (10 pp.). https://doi.org/10.1016/j.pnucene.2024.105430
DORA PSI
Tagliente G, Milazzo PM, Paradela C, Kopecky S, Vescovi D, Alaerts G, et al.
High-resolution cross section measurements for neutron interactions on ⁸⁹Y with incident neutron energies up to 95 keV
European Physical Journal A: Hadrons and Nuclei. 2024; 60(1): 21 (18 pp.). https://doi.org/10.1140/epja/s10050-024-01243-4
DORA PSI
Tai CK, Mao J, Petrov V, Manera A, Bolotnov IA
Study of stable stratification in HiRJET facility with direct numerical simulation
Nuclear Science and Engineering. 2024; 198(7): 1347-1370. https://doi.org/10.1080/00295639.2023.2197656
DORA PSI
Valori V, Qin S, Petrov V, Manera A
High-fidelity velocity and concentration measurements of turbulent Buoyant Jets
Nuclear Technology. 2024. https://doi.org/10.1080/00295450.2024.2355406
DORA PSI
Verma L, Clifford I, Konarski P, Scolaro A, Ferroukhi H
OFFBEAT V&V studies for REBEKA tests on cladding ballooning and burst during LOCA conditions
Annals of Nuclear Energy. 2024; 208: 110773 (14 pp.). https://doi.org/10.1016/j.anucene.2024.110773
DORA PSI
Yilgor I, Sellers ZD, Hartvigsen JL, Sweetland KM, Huang P-H, Ahn T, et al.
Recent developments and findings of heat pipe experiments for microreactor applications
Nuclear Technology. 2024. https://doi.org/10.1080/00295450.2024.2375488
DORA PSI

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2023

Ahn T, Diaz J, Adams R, Petrov V, Manera A
Measurement of local void fraction of air water flow in the 8 × 8 rod bundle using high-resolution gamma-ray tomography
Nuclear Technology. 2023; 209: 1898-1913. https://doi.org/10.1080/00295450.2023.2197680
DORA PSI
Al-Yahia OS, Clifford I, Bissels W-M, Suckow D, Ferroukhi H
Experimental study for high Reynolds’ gas-liquid two-phase flow through rod bundle using Wire Mesh Sensor (WMS)
Nuclear Engineering and Design. 2023; 405: 112224 (23 pp.). https://doi.org/10.1016/j.nucengdes.2023.112224
DORA PSI
Al-Yahia OS, Clifford I, Nikitin K, Liu P, Ferroukhi H
TRACE code simulation of the interaction between reactor coolant system and containment building with passive heat removal system
Nuclear Engineering and Design. 2023; 406: 112234 (21 pp.). https://doi.org/10.1016/j.nucengdes.2023.112234
DORA PSI
Alhassan E, Rochman D, Vasiliev A, Koning AJ, Ferroukhi H
TENDL-based evaluation and adjustment of p+¹¹¹Cd between 1 and 100 MeV
Applied Radiation and Isotopes. 2023; 198: 110832 (15 pp.). https://doi.org/10.1016/j.apradiso.2023.110832
DORA PSI
Auchmann B, Araujo DM, Brem A, Daly M, Felder R, Feuvrier J, et al.
Test results from CD1 Short CCT Nb₃Sn dipole demonstrator and considerations about CCT technology for the FCC-hh main dipole
IEEE Transactions on Applied Superconductivity. 2023; 34(5): 4000906 (6 pp.). https://doi.org/10.1109/TASC.2023.3344425
DORA PSI
Berry L, Truchet G, Bonaccorsi T
Accelerated Monte Carlo perturbation calculation by surface recovery
Annals of Nuclear Energy. 2023; 185: 109716 (11 pp.). https://doi.org/10.1016/j.anucene.2023.109716
DORA PSI
Bourdot Dutra C da S, Merzari E, Acierno J, Kraus A, Manera A, Petrov V, et al.
High-fidelity modeling and experiments to inform safety analysis codes for heat pipe microreactors
Nuclear Technology. 2023; 209: 1592-1616. https://doi.org/10.1080/00295450.2023.2181040
DORA PSI
Breitenmoser D, Prasser HM, Manera A, Petrov V
Machine learning based flow regime recognition in helically coiled tubes using X-ray radiography
International Journal of Multiphase Flow. 2023; 161: 104382 (10 pp.). https://doi.org/10.1016/j.ijmultiphaseflow.2023.104382
DORA PSI
Cavaliere A, Marone F, Cozzo C, Buchanan K, Lorrette C, Pouchon MA
FEM heat transfer modelling with tomography-based SiC_f/SiC unit cell
High Temperatures-High Pressures. 2023; 52(2): 95-110. https://doi.org/10.32908/hthp.v52.1281
DORA PSI
Cherezov A, Vasiliev A, Ferroukhi H
Acceleration of nuclear reactor simulation and uncertainty quantification using low-precision arithmetic
Applied Sciences. 2023; 13(2): 896 (14 pp.). https://doi.org/10.3390/app13020896
DORA PSI
Coindreau O, Herranz LE, Bocanegra R, Ederli S, Maccari P, Mascari F, et al.
Uncertainty quantification for a severe accident sequence in a SFP in the frame of the H-2020 project MUSA: first outcomes
Annals of Nuclear Energy. 2023; 188: 109796 (9 pp.). https://doi.org/10.1016/j.anucene.2023.109796
DORA PSI
Dehbi A, Kapulla R
CFD analyses of large-scale tests highlighting the effects of thermal radiation in steam-containing atmospheres
Nuclear Engineering and Design. 2023; 415: 112710 (12 pp.). https://doi.org/10.1016/j.nucengdes.2023.112710
DORA PSI
Diaz J, Liu Q, Petrov V, Manera A, Sun X
High-resolution X-Ray radiography methods developed for Post-CHF experiment
Nuclear Technology. 2023; 209(10): 1442-1465. https://doi.org/10.1080/00295450.2022.2133504
DORA PSI
Dokhane A, Vasiliev A, Hursin M, Ferroukhi H
Nuclear data effect on BWR stability parameter uncertainty at stable core conditions
Nuclear Engineering and Design. 2023; 414: 112620 (9 pp.). https://doi.org/10.1016/j.nucengdes.2023.112620
DORA PSI
Domingo-Pardo C, Babiano-Suarez V, Balibrea-Correa J, Caballero L, Ladarescu I, Lerendegui-Marco J, et al.
Advances and new ideas for neutron-capture astrophysics experiments at CERN n_TOF
European Physical Journal A: Hadrons and Nuclei. 2023; 59(1): 8 (11 pp.). https://doi.org/10.1140/epja/s10050-022-00876-7
DORA PSI
Fogliatto E, Puragliesi R, Clifford I, Ferroukhi H
Assessment of the influence of scaling on turbulent mixing in downcomer and core-inlet flow distribution
Annals of Nuclear Energy. 2023; 185: 109715 (15 pp.). https://doi.org/10.1016/j.anucene.2023.109715
DORA PSI
Frankl M, Wittel M, Diomidis N, Vasiliev A, Ferroukhi H, Pudollek S
Criticality assessments for long-term post-closure canister corrosion scenarios in a deep geological repository
Annals of Nuclear Energy. 2023; 180: 109449 (9 pp.). https://doi.org/10.1016/j.anucene.2022.109449
DORA PSI
Garbil R, Hadj Hassine SB, Blaise P, Ferry C, Sjöland A, Christensen P, et al.
Spent nuclear fuel management, characterisation, and dissolution behaviour: progress and achievement from SFC and DisCo
EPJ Nuclear Sciences and Technologies. 2023; 9: 2022029 (12 pp.). https://doi.org/10.1051/epjn/2022029
DORA PSI
Gonzalez-Amoros J, Papadionysiou M, Kim S, Joo HG
Capability extension of the high-resolution thermal-hydraulic code ESCOT for hexagonal geometry core multiphysics analysis
Nuclear Science and Engineering. 2023; 197(8): 1634-1655. https://doi.org/10.1080/00295639.2022.2140577
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 – overview and first results
Nuclear Engineering and Design. 2023; 404: 112189 (20 pp.). https://doi.org/10.1016/j.nucengdes.2023.112189
DORA PSI
Hursin M, Zoia A, Rouchon A, Brighenti A, Zmijarevic I, Santandrea S, et al.
Modeling noise experiments performed at AKR-2 and CROCUS zero-power reactors
Annals of Nuclear Energy. 2023; 194: 110066 (16 pp.). https://doi.org/10.1016/j.anucene.2023.110066
DORA PSI
Huxford A, Coppo Leite V, Merzari E, Zou L, Petrov V, Manera A
A hybrid domain overlapping method for coupling System Thermal Hydraulics and CFD codes
Annals of Nuclear Energy. 2023; 189: 109842 (11 pp.). https://doi.org/10.1016/j.anucene.2023.109842
DORA PSI
Jäckel BS, Birchley JC, Lind T, Steinbrück M, Park S
Nitriding model for zirconium based fuel cladding in severe accident codes
Journal of Nuclear Materials. 2023; 582: 154466 (7 pp.). https://doi.org/10.1016/j.jnucmat.2023.154466
DORA PSI
Kang S, Huang PH, Petrov V, Manera A, Ahn T, Kammenzind B, et al.
Determination of the hydrogen heat of transport in Zircaloy-4
Journal of Nuclear Materials. 2023; 573: 154122 (10 pp.). https://doi.org/10.1016/j.jnucmat.2022.154122
DORA PSI
Kapulla R, Xiongguo L, Kelm S, Doll U, Paranjape S, Paladino D
Importance, influence and limits of CFD radiation modeling for containment atmosphere simulations
Nuclear Engineering and Design. 2023; 411: 112408 (12 pp.). https://doi.org/10.1016/j.nucengdes.2023.112408
DORA PSI
Khvostov G
Analysis of thermal fuel behaviour under steady-state irradiation using selected cases of the IAEA CRP FUMEX
Journal of Nuclear Materials. 2023; 584: 154589 (8 pp.). https://doi.org/10.1016/j.jnucmat.2023.154589
DORA PSI
Khvostov G
Calibration and validation of thermal fuel behaviour models based on the first case of the first IAEA CRP FUMEX
Journal of Nuclear Materials. 2023; 584: 154588 (11 pp.). https://doi.org/10.1016/j.jnucmat.2023.154588
DORA PSI
Khvostov G
Insights into fuel behaviour during relatively fast thermal transients based on calculations for two tests of the Halden IFA-507 experiment
Nuclear Engineering and Technology. 2023; 55(10): 3801-3807. https://doi.org/10.1016/j.net.2023.06.045
DORA PSI
Konarski P, Cozzo C, Khvostov G, Ferroukhi H
Modeling of hydrogen behavior in liner claddings
Journal of Nuclear Materials. 2023; 573: 154125 (11 pp.). https://doi.org/10.1016/j.jnucmat.2022.154125
DORA PSI
Laureau A, Gruel A, Lamirand V, Ligonnet T, Sardet A, Pautz A
Analysis of the preliminary campaign for the PETALE program
EPJ Nuclear Sciences and Technologies. 2023; 9: 25 (9 pp.). https://doi.org/10.1051/epjn/2023010
DORA PSI
Lee H, Vasiliev A, Ferroukhi H
Addressing practical aspects of the nuclear criticality safety evaluations with frequentist statistics
Annals of Nuclear Energy. 2023; 181: 109556 (17 pp.). https://doi.org/10.1016/j.anucene.2022.109556
DORA PSI
Malicki M, Lind T
Impact of PSI-KIT nitriding model on hypothetical spent fuel pool accident simulation
Nuclear Engineering and Technology. 2023; 55(7): 2504-2515. https://doi.org/10.1016/j.net.2023.04.003
DORA PSI
Malicki M, Lind T
Parametric MELCOR 2.2 sensitivity and uncertainty study with a focus on aerosols based on Phébus test FPT1
Progress in Nuclear Energy. 2023; 158: 104609 (15 pp.). https://doi.org/10.1016/j.pnucene.2023.104609
DORA PSI
Mao J, Petrov V, Manera A, Howard TK, Cetiner SM
On the development of a novel acoustic flowmeter for high-temperature gas-cooled reactors
Nuclear Technology. 2023; 209(10). https://doi.org/10.1080/00295450.2022.2133505
DORA PSI
Mascari F, Bersano A, Adorni M, D'Ovidio G, Martín-Fuertes F, Jin XZ, et al.
Current status of MELCOR 2.2 for fusion safety analyses
Fusion Engineering and Design. 2023; 194: 113869 (7 pp.). https://doi.org/10.1016/j.fusengdes.2023.113869
DORA PSI
Michalopoulou V, Stamatopoulos A, Diakaki M, Tsinganis A, Vlastou R, Kokkoris M, et al.
Measurement of the neutron-induced fission cross section of ²³⁰Th at the CERN n_TOF facility
Physical Review C: Nuclear Physics. 2023; 108(1): 014616 (15 pp.). https://doi.org/10.1103/PhysRevC.108.014616
DORA PSI
Miniero L, Pandey K, Fredrich D, Shcherbanev S, Doll U, Giusti A, et al.
Air-blast atomization and ignition of a kerosene spray in hot vitiated crossflow
Combustion and Flame. 2023; 256: 112915 (13 pp.). https://doi.org/10.1016/j.combustflame.2023.112915
DORA PSI
Otten S, Kario A, Wessel WAJ, Leferink J, Ten Kate HHJ, Daly M, et al.
Training curves of Nb₃Sn Rutherford cables with a wide range of impregnation materials measured in the BOX facility
IEEE Transactions on Applied Superconductivity. 2023; 33(5): 4003605 (5 pp.). https://doi.org/10.1109/TASC.2023.3267051
DORA PSI
Paladino D, Kapulla R, Paranjape S, Suter S, Hug C, Chae M-S, et al.
PANDA experimental database and further needs for containment analyses
Nuclear Engineering and Design. 2023; 404: 112173 (18 pp.). https://doi.org/10.1016/j.nucengdes.2023.112173
DORA PSI
Pandey K, Miniero L, Doll U, de Oliveira PM, Mastorakos E, Noiray N
Topological transitions of Jet A-1 lean azimuthal flames (LEAF)
Proceedings of the Combustion Institute. 2023; 39(4): 4791-4799. https://doi.org/10.1016/j.proci.2022.08.034
DORA PSI
Patronis N, Mengoni A, Goula S, Aberle O, Alcayne V, Altieri S, et al.
Status report of the n_TOF facility after the 2nd CERN long shutdown period
EPJ Techniques and Instrumentation. 2023; 10(1): 13 (10 pp.). https://doi.org/10.1140/epjti/s40485-023-00100-w
DORA PSI
Pelloni S, Rochman D
Testing JENDL-5 data for U-235, Pu-239 and U-238 above the resolved resonance region
Annals of Nuclear Energy. 2023; 182: 109603 (10 pp.). https://doi.org/10.1016/j.anucene.2022.109603
DORA PSI
Rochman D, Taforeau J, Simeonov T, Shama A
Comparison of calculated and measured spent nuclear fuel decay heat with CASMO5, SNF and standard methods
Nuclear Engineering and Design. 2023; 410: 112392 (9 pp.). https://doi.org/10.1016/j.nucengdes.2023.112392
DORA PSI
Rochman DA, Álvarez-Velarde F, Dagan R, Fiorito L, Häkkinen S, Kromar M, et al.
On the estimation of nuclide inventory and decay heat: a review from the EURAD European project
EPJ Nuclear Sciences and Technologies. 2023; 9: 14 (24 pp.). https://doi.org/10.1051/epjn/2022055
DORA PSI
Seidl M, Schillebeeckx P, Rochman D
Note on the potential to increase the accuracy of source term calculations for spent nuclear fuel
Frontiers in Energy Research. 2023; 11: 1143312 (15 pp.). https://doi.org/10.3389/fenrg.2023.1143312
DORA PSI
Shama A, Caruso S, Rochman D
Analyses of the bias and uncertainty of SNF decay heat calculations using Polaris and ORIGEN
Frontiers in Energy Research. 2023; 11: 1161076 (18 pp.). https://doi.org/10.3389/fenrg.2023.1161076
DORA PSI
Siefman D, Hursin M, Percher C, Heinrichs D
Uncertainty quantification of a light water pulsed-neutron die-away experiment to thermal neutron scattering laws
Nuclear Science and Engineering. 2023; 197: 14-24. https://doi.org/10.1080/00295639.2022.2103344
DORA PSI
Sosnin NV, Lederer-Woods C, Krtička M, Garg R, Dietz M, Bacak M, et al.
Measurement of the ⁷⁷Se (n, γ) cross section up to 200 keV at the n_TOF facility at CERN
Physical Review C: Nuclear Physics. 2023; 107(6): 065805 (9 pp.). https://doi.org/10.1103/PhysRevC.107.065805
DORA PSI
Torres-Sánchez P, Praena J, Porras I, Sabaté-Gilarte M, Lederer-Woods C, Aberle O, et al.
Measurement of the ¹⁴N(n, p) ¹⁴C cross section at the CERN n_TOF facility from subthermal energy to 800 keV
Physical Review C: Nuclear Physics. 2023; 107(6): 064617 (15 pp.). https://doi.org/10.1103/PhysRevC.107.064617
DORA PSI
Vocke M, Kapulla R, Morton C, Klein M, Martinuzzi RJ
Advection-based temporal reconstruction technique for turbulent velocity fields
Physics of Fluids. 2023; 35(1): 015123 (18 pp.). https://doi.org/10.1063/5.0129564
DORA PSI
Ványi AS, Hursin M, Czifrus S
Analysis of transient measurements with thermal feedback and coupled TRACE/PARCS calculations performed on the BME Training Reactor
Annals of Nuclear Energy. 2023; 194: 110072 (15 pp.). https://doi.org/10.1016/j.anucene.2023.110072
DORA PSI
Ványi AS, Hursin M, Aszódi A, Adorján L, Biró B, Magyar B, et al.
Thermal-hydraulic measurements and TRACE system code analysis performed on the natural circulation cooled BME Training Reactor
Annals of Nuclear Energy. 2023; 189: 109839 (12 pp.). https://doi.org/10.1016/j.anucene.2023.109839
DORA PSI
Vázquez-Rodríguez C, Andreani M, Jiménez G, Kapulla R, Paranjape S, Manuel Martín-Valdepeñas J, et al.
Assessment of the depressurisation and mixing effects of two spray systems in the PANDA facility, part II – simulations using GOTHIC8.3(QA)
Nuclear Engineering and Design. 2023; 403: 112120 (20 pp.). https://doi.org/10.1016/j.nucengdes.2022.112120
DORA PSI
Vázquez-Rodríguez C, Kapulla R, Paranjape S, Andreani M, Jiménez G, Martín-Valdepeñas JM, et al.
Assessment of the depressurization and mixing effects of two spray systems in the PANDA facility, part I - experimental results
Nuclear Engineering and Design. 2023; 412: 112453 (11 pp.). https://doi.org/10.1016/j.nucengdes.2023.112453
DORA PSI
Welker Z, Manera A, Petrov V, Balestra P
An experimental and theoretical examination of air ingress rates during small- and medium-break air ingress accidents
Nuclear Technology. 2023; 209(10): 1577-1591. https://doi.org/10.1080/00295450.2022.2134673
DORA PSI
Wolfertz A, Adams R, Perret G, Lamirand V
Development of a multi-channel gamma-blind fast neutron detector based on wavelength shifting fibers embedded in a ZnS:Ag epoxy mixture
Nuclear Instruments and Methods in Physics Research, Section A: Accelerators, Spectrometers, Detectors and Associated Equipment. 2023; 1053: 168385 (12 pp.). https://doi.org/10.1016/j.nima.2023.168385
DORA PSI
Wolfertz A, Perret G, Adams R
Non-destructive analysis of spent fuel samples using a gamma-blind fast neutron detector
Annals of Nuclear Energy. 2023; 188: 109792 (10 pp.). https://doi.org/10.1016/j.anucene.2023.109792
DORA PSI

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2022

Alhassan E, Rochman D, Vasiliev A, Hursin M, Koning AJ, Ferroukhi H
Iterative Bayesian Monte Carlo for nuclear data evaluation
Nuclear Science and Techniques. 2022; 33(4): 50 (31 pp.). https://doi.org/10.1007/s41365-022-01034-w
DORA PSI
Alyammahi N, Yoon HJ, Al-Yahia OS, Leung R
The scaling effect analysis of counterpart test between LSTF and ATLAS IET facilities on 1% top head break LOCA
Nuclear Engineering and Design. 2022; 397: 111917 (12 pp.). https://doi.org/10.1016/j.nucengdes.2022.111917
DORA PSI
Avrigeanu M, Rochman D, Koning AJ, Fischer U, Leichtle D, Costache C, et al.
Advanced breakup-nucleon enhancement of deuteron-induced reaction cross sections
European Physical Journal A: Hadrons and Nuclei. 2022; 58: 3 (13 pp.). https://doi.org/10.1140/epja/s10050-021-00659-6
DORA PSI
Cozzo C, Khvostov G, Clifford I, Ferroukhi H
Appraisal of the NRC H-uptake calculation for Swiss boiling water reactors
Nuclear Engineering and Design. 2022; 391: 111731 (5 pp.). https://doi.org/10.1016/j.nucengdes.2022.111731
DORA PSI
Di Giuli M, Malicki M, Dejardin P, Corda V, Swaidan AM
MELCOR 2.2-ASTEC V2.2 crosswalk study reproducing SBLOCA and CSBO scenarios in a PWR1000-like reactor part I: analysis of RCS thermal-hydraulics and in-vessel phenomena
Nuclear Engineering and Design. 2022; 387: 111248 (22 pp.). https://doi.org/10.1016/j.nucengdes.2021.111248
DORA PSI
Diaz J, Serrano-Aguilera JJ, Petrov V, Manera A
Development of a more accurate dynamic bias error model for two-phase flow measurements performed with radiation transmission
International Journal of Multiphase Flow. 2022; 146: 103881 (22 pp.). https://doi.org/10.1016/j.ijmultiphaseflow.2021.103881
DORA PSI
Dokhane A, Vasiliev A, Hursin M, Rochman D, Ferroukhi H
A critical study on best methodology to perform UQ for RIA transients and application to SPERT-III experiments
Nuclear Engineering and Technology. 2022; 54(5): 1804-1812. https://doi.org/10.1016/j.net.2021.10.042
DORA PSI
Dokhane A, Vasiliev A, Ferroukhi H
On butterfly effect in the dynamics of Oskarshamn-2 instability event of 1999
Nuclear Engineering and Design. 2022; 399: 112016 (12 pp.). https://doi.org/10.1016/j.nucengdes.2022.112016
DORA PSI
Doll U, Migliorini M, Baikie J, Zachos PK, Röhle I, Melnikov S, et al.
Non-intrusive flow diagnostics for unsteady inlet flow distortion measurements in novel aircraft architectures
Progress in Aerospace Sciences. 2022; 130: 100810 (24 pp.). https://doi.org/10.1016/j.paerosci.2022.100810
DORA PSI
Doll U, Röhle I, Dues M, Kapulla R
Time-resolved multi-parameter flow diagnostics by filtered Rayleigh scattering: system design through multi-objective optimisation
Measurement Science and Technology. 2022; 33(10): 105204 (12 pp.). https://doi.org/10.1088/1361-6501/ac7cca
DORA PSI
Downing JR, Petrov V, Manera A
3D field data of flow structures in dead-ended, coolant loop reactor branch lines for CFD validation of thermal fatigue onset modeling
Nuclear Engineering and Design. 2022; 399: 112012 (10 pp.). https://doi.org/10.1016/j.nucengdes.2022.112012
DORA PSI
Fagnoni F, Konarski P
Hydrogen degassing of zirconium under high-vacuum conditions
Metals. 2022; 12(5): 868 (9 pp.). https://doi.org/10.3390/met12050868
DORA PSI
Fiorina C, Clifford I, Kelm S, Lorenzi S
On the development of multi-physics tools for nuclear reactor analysis based on OpenFOAM®: state of the art, lessons learned and perspectives
Nuclear Engineering and Design. 2022; 387: 111604 (15 pp.). https://doi.org/10.1016/j.nucengdes.2021.111604
DORA PSI
Fogliatto EO, Clausse A, Teruel FE
Development of a double-MRT pseudopotential model for tridimensional boiling simulation
International Journal of Thermal Sciences. 2022; 179: 107637 (13 pp.). https://doi.org/10.1016/j.ijthermalsci.2022.107637
DORA PSI
Janasz F, Prasser H-M, Suckow D, Mityakov A
The use of a novel gradient heat flux sensor for characterization of reflux condensation
Nuclear Engineering and Design. 2022; 395: 111885 (9 pp.). https://doi.org/10.1016/j.nucengdes.2022.111885
DORA PSI
Jang J, Hursin M, Lee W, Pautz A, Papadionysiou M, Ferroukhi H, et al.
Analysis of Rostov-II benchmark using conventional two-step code systems
Energies. 2022; 15(9): 3318 (24 pp.). https://doi.org/10.3390/en15093318
DORA PSI
Jansson P, Bengtsson M, Bäckström U, Álvarez-Velarde F, Čalič D, Caruso S, et al.
Blind benchmark exercise for spent nuclear fuel decay heat
Nuclear Science and Engineering. 2022; 196(9): 1125-1145. https://doi.org/10.1080/00295639.2022.2053489
DORA PSI
Kalilainen J, Lind T
Uncertainty quantification study on gas phase iodine release from Fukushima Daiichi accident in unit 3
Annals of Nuclear Energy. 2022; 166: 108740 (13 pp.). https://doi.org/10.1016/j.anucene.2021.108740
DORA PSI
Kapulla R, Paranjape S, Doll U, Kirkby E, Paladino D
Experimental assessment of thermal radiation effects on containment atmospheres with varying steam content
Nuclear Engineering and Technology. 2022; 54(11): 4348-4358. https://doi.org/10.1016/j.net.2022.07.001
DORA PSI
Kapulla R, Doll U, Kirkby E, Paranjape S, Paladino D
Growth laws and self-similarity in the confined mixing zone of unstratified and strongly stably stratified isokinetic mixing-layers past a splitter plate
Physics of Fluids. 2022; 34(3): 035129 (16 pp.). https://doi.org/10.1063/5.0082950
DORA PSI
Kapulla R, Paranjape S, Fehlmann M, Suter S, Doll U, Paladino D
The effects of activated cooler power on the transient pressure decay and helium mixing in the PANDA facility
Nuclear Engineering and Technology. 2022; 54(6): 2311-2320. https://doi.org/10.1016/j.net.2021.12.032
DORA PSI
Khvostov G
Modelling effects of transient FGR in LWR fuel rods during a LOCA
Journal of Nuclear Materials. 2022; 559: 153446 (26 pp.). https://doi.org/10.1016/j.jnucmat.2021.153446
DORA PSI
Maestre J, Bahamonde C, Lamas Garcia I, Kershaw K, Biancacci N, Busom J, et al.
High intensity proton beam impact at 440 GeV/c on Mo and Cu coated CfC/graphite and SiC/SiC absorbers for beam intercepting devices
Journal of Instrumentation. 2022; 17: P01019 (32 pp.). https://doi.org/10.1088/1748-0221/17/01/P01019
DORA PSI
Mager T, Fiorina C, Hursin M, Pautz A
Investigation and validation of unstructured mesh methodologies for modeling experimental reactors
Energies. 2022; 15(4): 1512 (11 pp.). https://doi.org/10.3390/en15041512
DORA PSI
Martinez-Quiroga V, Szogradi M, Schollenberger S, Sanchez-Perea M, Sandberg N, Zhongyun J, et al.
OECD/NEA PKL-4 benchmark activity. Code assessment of the relevant phenomena associated to a blind IBLOCA experiment
Nuclear Engineering and Design. 2022; 389: 111632 (20 pp.). https://doi.org/10.1016/j.nucengdes.2021.111632
DORA PSI
Moreno-Soto J, Valenta S, Berthoumieux E, Chebboubi A, Diakaki M, Dridi W, et al.
Constraints on the dipole photon strength for the odd uranium isotopes
Physical Review C: Nuclear Physics. 2022; 105(2): 024618 (14 pp.). https://doi.org/10.1103/PhysRevC.105.024618
DORA PSI
Nichenko S, Kalilainen J, Lind T
MSR simulation with cGEMS: fission product release and aerosol formation
Journal of Nuclear Engineering. 2022; 3(1): 105-116. https://doi.org/10.3390/jne3010006
DORA PSI
Nikitin K, Clifford I, Dokhane A, Ferroukhi H
Methodology for CPR estimations of BWR cycle specific transient reload analyses using CTF sub-channel code
Nuclear Engineering and Design. 2022; 389: 111649 (14 pp.). https://doi.org/10.1016/j.nucengdes.2022.111649
DORA PSI
Pakari OV, Lamirand V, Mager T, Frajtag P, Pautz A
High accuracy measurement of the prompt neutron decay constant in CROCUS using gamma noise and bootstrapped uncertainties
Annals of Nuclear Energy. 2022; 170: 109011 (9 pp.). https://doi.org/10.1016/j.anucene.2022.109011
DORA PSI
Paladino D, Kapulla R, Paranjape S, Suter S, Andreani M
PANDA experiments within the OECD/NEA HYMERES-2 project on containment hydrogen distribution, thermal radiation and suppression pool phenomena
Nuclear Engineering and Design. 2022; 392: 111777 (18 pp.). https://doi.org/10.1016/j.nucengdes.2022.111777
DORA PSI
Paladino D, Paranjape S, Mignot G, Kapulla R
Parametric study highlighting cooler and spray activation on the transient mixing of a three-gas composition in the PANDA facility
Progress in Nuclear Energy. 2022; 150: 104283 (9 pp.). https://doi.org/10.1016/j.pnucene.2022.104283
DORA PSI
Papadionysiou M, Kim S, Hursin M, Vasiliev A, Ferroukhi H, Pautz A, et al.
Validation of the novel core solver nTRACER/COBRA-TF for full core high fidelity cycle analysis of VVERs
Nuclear Engineering and Design. 2022; 398: 111946 (16 pp.). https://doi.org/10.1016/j.nucengdes.2022.111946
DORA PSI
Papadionysiou M, Kim S, Hursin M, Vasiliev A, Ferroukhi H, Pautz A, et al.
Verification and validation of the high-resolution code nTF with VVER-1000 hot zero power monte carlo calculations and experimental data
Annals of Nuclear Energy. 2022; 178: 109385 (34 pp.). https://doi.org/10.1016/j.anucene.2022.109385
DORA PSI
Papaoikonomou A, Wingate J, Verma V, Durrant A, Ioannou G, Papagiannis T, et al.
Deep learning techniques for in-core perturbation identification and localization of time-series nuclear plant measurements
Annals of Nuclear Energy. 2022; 178: 109373 (10 pp.). https://doi.org/10.1016/j.anucene.2022.109373
DORA PSI
Pelloni S, Rochman D
Adjustment of JEFF-3.3 data for U-235 and Pu-239 in the fast, non-resonant energy range
Annals of Nuclear Energy. 2022; 177: 109296 (10 pp.). https://doi.org/10.1016/j.anucene.2022.109296
DORA PSI
Perret G, Wicaksono D, Clifford ID, Ferroukhi H
Global sensitivity analysis and bayesian calibration on a series of reflood experiments with varying boundary conditions
Nuclear Technology. 2022; 208(4): 711-722. https://doi.org/10.1080/00295450.2021.1936879
DORA PSI
Rochman D, Vasiliev A, Ferroukhi H, Muñoz A, Vazquez Antolin M, Berrios Torres M, et al.
Analysis of ENRESA BWR samples: nuclide inventory and decay heat
EPJ Nuclear Sciences and Technologies. 2022; 8: 9 (16 pp.). https://doi.org/10.1051/epjn/2022007
DORA PSI
Rochman D, Vasiliev A, Ferroukhi H, Koning A, Sublet J-C
Impact of H in H₂O thermal scattering data on criticality calculation: uncertainty and adjustment
EPJ Nuclear Sciences and Technologies. 2022; 8: 3 (7 pp.). https://doi.org/10.1051/epjn/2021028
DORA PSI
Scolaro A, Fiorina C, Clifford I, Pautz A
Development of a semi-implicit contact methodology for finite volume stress solvers
International Journal for Numerical Methods in Engineering. 2022; 123(2): 309-338. https://doi.org/10.1002/nme.6857
DORA PSI
Scolaro A, Van Uffelen P, Schubert A, Fiorina C, Brunetto E, Clifford I, et al.
Towards coupling conventional with high-fidelity fuel behavior analysis tools
Progress in Nuclear Energy. 2022; 152: 104357 (12 pp.). https://doi.org/10.1016/j.pnucene.2022.104357
DORA PSI
Shama A, Rochman D, Caruso S, Pautz A
Validation of spent nuclear fuel decay heat calculations using Polaris, ORIGEN and CASMO5
Annals of Nuclear Energy. 2022; 165: 108758 (14 pp.). https://doi.org/10.1016/j.anucene.2021.108758
DORA PSI
Vidal-Ferràndiz A, Ginestar D, Carreño A, Verdú G, Dokhane A, Verma V, et al.
Modelling and simulations of reactor neutron noise induced by mechanical vibrations
Annals of Nuclear Energy. 2022; 177: 109300 (21 pp.). https://doi.org/10.1016/j.anucene.2022.109300
DORA PSI
Ványi AS, Hursin M, Czifrus S
Analysis of diffusion coefficient correction methods applied for small-core, high-leakage reactors
Annals of Nuclear Energy. 2022; 174: 109147 (11 pp.). https://doi.org/10.1016/j.anucene.2022.109147
DORA PSI
Wei Z, Ničeno B, Puragliesi R, Fogliatto E
Assessment of turbulent heat flux models for URANS simulations of turbulent buoyant flows in ROCOM tests
Nuclear Engineering and Technology. 2022; 54(11): 4359-4372. https://doi.org/10.1016/j.net.2022.07.009
DORA PSI
Yoon HJ, Alyammahi N, Al-Yahia OS, Leung R
Validation of RELAP5 MOD3.3 for 1% reactor pressure vessel top head break loss of coolant accident via the ATLAS facility
Nuclear Engineering and Design. 2022; 400: 112054 (14 pp.). https://doi.org/10.1016/j.nucengdes.2022.112054
DORA PSI
Yum S, Hursin M, Vasiliev A, Vinai P, Mylonakis AG, Demazière C, et al.
Uncertainty analyses of neutron noise simulations in a Zero-Power reactor
Annals of Nuclear Energy. 2022; 174: 109157 (13 pp.). https://doi.org/10.1016/j.anucene.2022.109157
DORA PSI

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2021

Adams R, Günther C, Höflich N, Pooth O
A 2D pixelated stilbene scintillator detector array for simultaneous radiography with fast neutrons and gammas
Journal of Instrumentation. 2021; 16(2): P02021 (21 pp.). https://doi.org/10.1088/1748-0221/16/02/P02021
DORA PSI
Amaducci S, Colonna N, Cosentino L, Cristallo S, Finocchiaro P, Krtička M, et al.
First results of the ¹⁴⁰Ce(n,ү)¹⁴¹Ce cross-section measurement at n_TOF
Universe. 2021; 7(6): 200 (11 pp.). https://doi.org/10.3390/UNIVERSE7060200
DORA PSI
Babiano-Suárez V, Lerendegui-Marco J, Balibrea-Correa J, Caballero L, Calvo D, Ladarescu I, et al.
Imaging neutron capture cross sections: i-TED proof-of-concept and future prospects based on Machine-Learning techniques
European Physical Journal A: Hadrons and Nuclei. 2021; 57(6): 197 (17 pp.). https://doi.org/10.1140/epja/s10050-021-00507-7
DORA PSI
Breitenmoser D, Papadopoulos P, Lind T, Prasser H-M
Droplet size distribution in a full-scale rectangular self-priming Venturi scrubber with liquid film injection
International Journal of Multiphase Flow. 2021; 142: 103694 (15 pp.). https://doi.org/10.1016/j.ijmultiphaseflow.2021.103694
DORA PSI
Choi YJ, Kam DH, Padopoulos P, Lind T, Jeong YH
Experimental investigation on bubble behaviors in a water pool using the venturi scrubbing nozzle
Nuclear Engineering and Technology. 2021; 53: 1756-1768. https://doi.org/10.1016/j.net.2020.11.024
DORA PSI
Clifford I, Ferroukhi H
Assessing the effects of switching from multi-channel to three-dimensional nodalisations of the core in TRACE
Nuclear Engineering and Design. 2021; 383: 111446 (15 pp.). https://doi.org/10.1016/j.nucengdes.2021.111446
DORA PSI
Dokhane A, Hursin M, Vasiliev A, Rochman D, Ferroukhi H
Recent developments in PSI BEPU analysis for SPERT-III RIA transient: ND uncertainty breakdown and kinetic parameters uncertainty assessment
Nuclear Engineering and Design. 2021; 382: 111378 (14 pp.). https://doi.org/10.1016/j.nucengdes.2021.111378
DORA PSI
Doll U, Barro C, Todino M, Boulouchos K
Impact of a split injection strategy on mixing, ignition and combustion behavior in premixed charge compression ignition combustion
Fuel. 2021; 294: 120511 (14 pp.). https://doi.org/10.1016/j.fuel.2021.120511
DORA PSI
Falsetti C, Kapulla R, Paranjape S, Paladino D
Thermal radiation, its effect on thermocouple measurements in the PANDA facility and how to compensate it
Nuclear Engineering and Design. 2021; 375: 111077 (9 pp.). https://doi.org/10.1016/j.nucengdes.2021.111077
DORA PSI
Frankl M, Hursin M, Rochman D, Vasiliev A, Ferroukhi H
Nuclear data uncertainty quantification in criticality safety evaluations for spent nuclear fuel geological disposal
Applied Sciences. 2021; 11(14): 6499 (19 pp.). https://doi.org/10.3390/app11146499
DORA PSI
Kapulla R, Manohar KH, Paranjape S, Paladino D
Self-similarity for statistical properties in low-order representations of a large-scale turbulent round jet based on the proper orthogonal decomposition
Experimental Thermal and Fluid Science. 2021; 123: 110320 (16 pp.). https://doi.org/10.1016/j.expthermflusci.2020.110320
DORA PSI
Khvostov G, Gorzel A
FALCON code-based analysis of PWR fuel rod behaviour during RIA transients versus new U.S.NRC and current Swiss failure limits
Nuclear Engineering and Technology. 2021; 53(11): 3741-3758. https://doi.org/10.1016/j.net.2021.06.001
DORA PSI
Konarski P, Cozzo C, Khvostov G, Ferroukhi H
Spent nuclear fuel in dry storage conditions – current trends in fuel performance modeling
Journal of Nuclear Materials. 2021; 555: 153138 (26 pp.). https://doi.org/10.1016/j.jnucmat.2021.153138
DORA PSI
Kromer H, Adams R, Prasser H-M
Development, design, and testing of a microwave-driven compact rotating-target D-D fast neutron generator for imaging applications
Applied Radiation and Isotopes. 2021; 174: 109715 (14 pp.). https://doi.org/10.1016/j.apradiso.2021.109715
DORA PSI
Lind T, Pellegrini M, Herranz LE, Sonnenkalb M, Nishi Y, Tamaki H, et al.
Overview and outcomes of the OECD/NEA benchmark study of the accident at the Fukushima Daiichi NPS (BSAF), Phase 2 – Results of severe accident analyses for unit 3
Nuclear Engineering and Design. 2021; 376: 111138 (12 pp.). https://doi.org/10.1016/j.nucengdes.2021.111138
DORA PSI
Nichenko S, Kalilainen J, Fernandez Moguel L, Lind T
Modelling of fission products release in VERDON-1 experiment with cGEMS: coupling of severe accident code MELCOR with GEMS thermodynamic modelling package
Annals of Nuclear Energy. 2021; 152: 107972 (11 pp.). https://doi.org/10.1016/j.anucene.2020.107972
DORA PSI
Pakari O, Mager T, Lamirand V, Frajtag P, Pautz A
Delayed gamma fraction determination in the zero power reactor CROCUS
EPJ Nuclear Sciences and Technologies. 2021; 7: 16 (6 pp.). https://doi.org/10.1051/epjn/2021015
DORA PSI
Pelloni S, Rochman D
Addressing challenges in nuclear data adjustment techniques using integral experiments based upon uranium solution thermal systems
Annals of Nuclear Energy. 2021; 163: 108590 (12 pp.). https://doi.org/10.1016/j.anucene.2021.108590
DORA PSI
Pázsit I, Torres LA, Hursin M, Nylén H, Dykin V, Montalvo C
Development of a new method to determine the axial void velocity profile in BWRs from measurements of the in-core neutron noise
Progress in Nuclear Energy. 2021; 138: 103805 (11 pp.). https://doi.org/10.1016/j.pnucene.2021.103805
DORA PSI
Pérot B, Carasco C, Eléon C, Bernard S, Sardet A, El Kanawati W, et al.
Sea container inspection with tagged neutrons
EPJ Nuclear Sciences and Technologies. 2021; 7: 6 (37 pp.). https://doi.org/10.1051/epjn/2021004
DORA PSI
Rochman D, Vasiliev A, Ferroukhi H, Hursin M
Analysis for the ARIANE BM1 and BM3 samples: nuclide inventory and decay heat
EPJ Nuclear Sciences and Technologies. 2021; 7: 18 (24 pp.). https://doi.org/10.1051/epjn/2021017
DORA PSI
Rochman D, Vasiliev A, Ferroukhi H, Hursin M
Analysis for the ARIANE GU1 sample: nuclide inventory and decay heat
Annals of Nuclear Energy. 2021; 160: 108359 (19 pp.). https://doi.org/10.1016/j.anucene.2021.108359
DORA PSI
Rochman D, Vasiliev A, Ferroukhi H, Hursin M, Ichou R, Taforeau J, et al.
Analysis for the ARIANE GU3 sample: nuclide inventory and decay heat
EPJ Nuclear Sciences and Technologies. 2021; 7: 14 (24 pp.). https://doi.org/10.1051/epjn/2021013
DORA PSI
Rochman DA, Bauge E
Fission yields and cross sections: correlated or not?
EPJ Nuclear Sciences and Technologies. 2021; 7: 5 (9 pp.). https://doi.org/10.1051/epjn/2021005
DORA PSI
Rochman D, Hursin M, Vasiliev A, Ferroukhi H
Impact of H in H₂O thermal scattering data on depletion calculation: k_∞, nuclide inventory and decay heat
EPJ Nuclear Sciences and Technologies. 2021; 7: 24 (8 pp.). https://doi.org/10.1051/epjn/2021027
DORA PSI
Rochman D, Shama A, Pudollek S, Caruso S, Pautz A
Uncertainty analyses of spent nuclear fuel decay heat calculations using SCALE modules
Nuclear Engineering and Technology. 2021; 53(9): 2816-2829. https://doi.org/10.1016/j.net.2021.03.013
DORA PSI
Schnabel G, Sjöstrand H, Hansson J, Rochman D, Koning A, Capote R
Conception and software implementation of a nuclear data evaluation pipeline
Nuclear Data Sheets. 2021; 173: 239-284. https://doi.org/10.1016/j.nds.2021.04.007
DORA PSI
Scolaro A, Van Uffelen P, Fiorina C, Schubert A, Clifford I, Pautz A
Investigation on the effect of eccentricity for fuel disc irradiation tests
Nuclear Engineering and Technology. 2021; 53(5): 1602-1611. https://doi.org/10.1016/j.net.2020.11.003
DORA PSI
Siefman D, Hursin M, Schnabel G, Sjöstrand H
Development and application of marginal likelihood optimization for integral parameter adjustment
Annals of Nuclear Energy. 2021; 159: 108255 (10 pp.). https://doi.org/10.1016/j.anucene.2021.108255
DORA PSI
Skolik K, Allison C, Hohorst J, Malicki M, Perez-Ferragut M, Pieńkowski L, et al.
Analysis of loss of coolant accident without ECCS and DHRS in an integral pressurized water reactor using RELAP/SCDAPSIM
Progress in Nuclear Energy. 2021; 134: 103648 (15 pp.). https://doi.org/10.1016/j.pnucene.2021.103648
DORA PSI
Sobes V, de Saint Jean C, Rochman D, Cabellos O, Holcomb A, Bauge E, et al.
WPEC Subgroup 44 computational inter-comparison exercise on correlations in nuclear data libraries
Annals of Nuclear Energy. 2021; 164: 108605 (9 pp.). https://doi.org/10.1016/j.anucene.2021.108605
DORA PSI
Solans V, Rochman D, Brazell C, Vasiliev A, Ferroukhi H, Pautz A
Optimisation of used nuclear fuel canister loading using a neural network and genetic algorithm
Neural Computing & Applications. 2021; 33: 16627-16639. https://doi.org/10.1007/s00521-021-06258-2
DORA PSI
Soubelet B, Adams R, Prasser H-M
Computed tomography combined with a material decomposition technique using a compact deuterium-deuterium (D-D) fast neutron generator
Radiation Physics and Chemistry. 2021; 181: 109296 (11 pp.). https://doi.org/10.1016/j.radphyschem.2020.109296
DORA PSI
Stuckert J, Steinbrueck M, Kalilainen J, Lind T, Birchley J
Experimental and modelling results of the QUENCH-18 bundle experiment on air ingress, cladding melting and aerosol release
Nuclear Engineering and Design. 2021; 379: 111267 (11 pp.). https://doi.org/10.1016/j.nucengdes.2021.111267
DORA PSI
Torres Delgado LA, Verma V, Montalvo C, Dokhane A, García-Berrocal A
Operational modal analysis for characterization of mechanical and thermal-hydraulic fluctuations in simulated neutron noise
Nuclear Engineering and Design. 2021; 373: 111017 (18 pp.). https://doi.org/10.1016/j.nucengdes.2020.111017
DORA PSI
Verma V, Chionis D, Dokhane A, Ferroukhi H
Studies of reactor noise response to vibrations of reactor internals and thermal-hydraulic fluctuations in PWRs
Annals of Nuclear Energy. 2021; 157: 108212 (19 pp.). https://doi.org/10.1016/j.anucene.2021.108212
DORA PSI
Ványi AS, Babcsány B, Böröczki ZI, Horváth A, Hursin M, Szieberth M, et al.
Steady-state neutronic measurements and comprehensive numerical analysis for the BME training reactor
Annals of Nuclear Energy. 2021; 155: 108144 (15 pp.). https://doi.org/10.1016/j.anucene.2021.108144
DORA PSI
Weilenmann M, Doll U, Bombach R, Blondé A, Ebi D, Xiong Y, et al.
Linear and nonlinear entropy-wave response of technically-premixed jet-flames-array and swirled flame to acoustic forcing
Proceedings of the Combustion Institute. 2021; 38(4): 6135-6143. https://doi.org/10.1016/j.proci.2020.06.233
DORA PSI

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2020

Alhassan E, Rochman D, Sjöstrand H, Vasiliev A, Koning AJ, Ferroukhi H
Bayesian updating for data adjustments and multi-level uncertainty propagation within Total Monte Carlo
Annals of Nuclear Energy. 2020; 139: 107239 (14 pp.). https://doi.org/10.1016/j.anucene.2019.107239
DORA PSI
Andreani M, Kapulla R, Kelm S, Paladino D, Paranjape S
Analyses of gas stratification erosion by a vertical jet in presence of an obstacle using the GOTHIC code
Journal of Nuclear Engineering and Radiation Science. 2020; 6(2): 021110 (18 pp.). https://doi.org/10.1115/1.4046296
DORA PSI
Andreani M, Paranjape S
Gas mixing caused by interacting heat sources. Part ii: modelling
Nuclear Engineering and Design. 2020; 370: 110887 (16 pp.). https://doi.org/10.1016/j.nucengdes.2020.110887
DORA PSI
Betschart T, Lind T, Prasser H-M
Investigation of two-phase flow hydrodynamics under SGTR severe accident conditions
Nuclear Engineering and Design. 2020; 366: 110768 (14 pp.). https://doi.org/10.1016/j.nucengdes.2020.110768
DORA PSI
Chionis D, Dokhane A, Belblidia L, Ferroukhi H, Girardin G, Pautz A
Development and verification of a methodology for neutron noise response to fuel assembly vibrations
Annals of Nuclear Energy. 2020; 147: 107669 (15 pp.). https://doi.org/10.1016/j.anucene.2020.107669
DORA PSI
Fiorina C, Scolaro A, Siefman D, Hursin M, Pautz A
Artificial neural networks as surrogate models for uncertainty quantification and data assimilation in 2-D/3-D fuel performance studies
Journal of Nuclear Engineering. 2020; 1(1): 54-62. https://doi.org/10.3390/jne1010005
DORA PSI
Guerrero C, Lerendegui-Marco J, Paul M, Tessler M, Heinitz S, Domingo-Pardo C, et al.
Neutron capture on the s-process branching point ¹⁷¹Tm via time-of-flight and activation
Physical Review Letters. 2020; 125(14): 142701 (8 pp.). https://doi.org/10.1103/PhysRevLett.125.142701
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 2 - results of severe accident analyses for Unit 1
Nuclear Engineering and Design. 2020; 369: 110849 (7 pp.). https://doi.org/10.1016/j.nucengdes.2020.110849
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 using neutron noise techniques
Nuclear Technology. 2020; 206(10): 1566-1583. https://doi.org/10.1080/00295450.2019.1701906
DORA PSI
Hursin M, Pelloni S, Vasiliev A, Ferroukhi H
Treatment of the implicit effect in Shark-X
Annals of Nuclear Energy. 2020; 138: 107178 (14 pp.). https://doi.org/10.1016/j.anucene.2019.107178
DORA PSI
Jäckel BS, Steiner P, Klügel J-U
Loss-of-cooling accident calculations for the wet storage pool of NPP Gösgen/Däniken
Nuclear Engineering and Design. 2020; 370: 110839 (6 pp.). https://doi.org/10.1016/j.nucengdes.2020.110839
DORA PSI
Kalilainen J, Nichenko S, Krepel J
Evaporation of materials from the molten salt reactor fuel under elevated temperatures
Journal of Nuclear Materials. 2020; 533: 152134 (13 pp.). https://doi.org/10.1016/j.jnucmat.2020.152134
DORA PSI
Khvostov G
Analysis of cladding failure in a BWR fuel rod using a SLICE-DO model of the FALCON code
Nuclear Engineering and Technology. 2020; 52(12): 2887-2900. https://doi.org/10.1016/j.net.2020.05.015
DORA PSI
Khvostov G
Analytical criteria for fuel fragmentation and burst FGR during a LOCA
Nuclear Engineering and Technology. 2020; 52(10): 2402-2409. https://doi.org/10.1016/j.net.2020.03.009
DORA PSI
Khvostov G
Numerical simulation of the effects of localized cladding oxidation on LWR fuel rod design limits using a SLICE-DO model of the FALCON code
Nuclear Engineering and Technology. 2020; 52(1): 135-147. https://doi.org/10.1016/j.net.2019.07.010
DORA PSI
Kim W, Hursin M, Pautz A, Vincent L, Pavel F, Lee D
Determination of the activity inventory and associated uncertainty quantification for the CROCUS zero power research reactor
Annals of Nuclear Energy. 2020; 136: 107034 (14 pp.). https://doi.org/10.1016/j.anucene.2019.107034
DORA PSI
Konarski P, Cozzo C, Khvostov G, Ferroukhi H
Dry storage modeling activities at PSI: implementation and testing of a creep model for dry storage
Kerntechnik. 2020; 85(6): 419-425. https://doi.org/10.3139/124.200072
DORA PSI
Laureau A, Lamirand V, Rochman D, Pautz A
Uncertainty propagation based on correlated sampling technique for nuclear data applications
EPJ Nuclear Sciences and Technologies. 2020; 6: 8 (9 pp.). https://doi.org/10.1051/epjn/2020003
DORA PSI
Laureau A, Lamirand V, Rochman D, Pautz A
Uncertainty propagation for the design study of the PETALE experimental programme in the CROCUS reactor
EPJ Nuclear Sciences and Technologies. 2020; 6: 9 (8 pp.). https://doi.org/10.1051/epjn/2020004
DORA PSI
Lind T, Campbell S, Herranz LE, Kissane M, Song JH
A summary of fission-product-transport phenomena during SGTR severe accidents
Nuclear Engineering and Design. 2020; 363: 110635 (10 pp.). https://doi.org/10.1016/j.nucengdes.2020.110635
DORA PSI
Mala P, Pautz A
Development and verification of pin-by-pin homogenized simplified transport solver Tortin for PWR core analysis
Nuclear Engineering and Technology. 2020; 52(11): 2431-2441. https://doi.org/10.1016/j.net.2020.04.022
DORA PSI
Mazzone A, Cristallo S, Aberle O, Alaerts G, Alcayne V, Amaducci S, et al.
Measurement of the ¹⁵⁴Gd(n,γ) cross section and its astrophysical implications
Physics Letters, Section B: Nuclear, Elementary Particle and High-Energy Physics. 2020; 804: 135405 (6 pp.). https://doi.org/10.1016/j.physletb.2020.135405
DORA PSI
Mora DF, Costa Garrido O, Mukin R, Niffenegger M
Fracture mechanics analyses of a reactor pressure vessel under non-uniform cooling with a combined TRACE-XFEM approach
Engineering Fracture Mechanics. 2020; 238: 107258 (16 pp.). https://doi.org/10.1016/j.engfracmech.2020.107258
DORA PSI
Morató S, Bernal Á, Miró R, Roman JE, Verdú G
Calculation of λ modes of the multi-group neutron transport equation using the discrete ordinates and Finite Difference Method
Annals of Nuclear Energy. 2020; 137: 107077 (15 pp.). https://doi.org/10.1016/j.anucene.2019.107077
DORA PSI
Nakayoshi A, Rempe JL, Barrachin M, Bottomley D, Jacquemain D, Journeau C, et al.
Review of Fukushima Daiichi Nuclear Power Station debris endstate location in OECD/NEA preparatory study on analysis of fuel debris (PreADES) project
Nuclear Engineering and Design. 2020; 369: 110857 (15 pp.). https://doi.org/10.1016/j.nucengdes.2020.110857
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
Nuclear Science and Engineering. 2020; 194(11): 1056-1066. https://doi.org/10.1080/00295639.2020.1753418
DORA PSI
Paranjape S, Kapulla R, Mignot G, Paladino D
Gas mixing caused by interacting heat sources PART I: experiments
Nuclear Engineering and Design. 2020; 370: 110914 (14 pp.). https://doi.org/10.1016/j.nucengdes.2020.110914
DORA PSI
Pellegrini M, Herranz L, Sonnenkalb M, Lind T, Maruyama Y, Gauntt R, et al.
Main findings, remaining uncertainties and lessons learned from the OECD/NEA BSAF project
Nuclear Technology. 2020; 206(9): 1449-1463. https://doi.org/10.1080/00295450.2020.1724731
DORA PSI
Pelloni S, Rochman D
Resonance parameter adjustment in the resolved region based upon an Asymptotic Generalized Linear Least-Squares methodology in conjunction with the Monte Carlo method
Annals of Nuclear Energy. 2020; 145: 107509 (9 pp.). https://doi.org/10.1016/j.anucene.2020.107509
DORA PSI
Plompen AJM, Cabellos O, De Saint Jean C, Fleming M, Algora A, Angelone M, et al.
The joint evaluated fission and fusion nuclear data library, JEFF-3.3
European Physical Journal A: Hadrons and Nuclei. 2020; 56(7): 181 (108 pp.). https://doi.org/10.1140/epja/s10050-020-00141-9
DORA PSI
Puragliesi R
Assessment of a URANS CFD model for gravity driven flows: a comparison with OECD/PKL2 ROCOM experiments
Nuclear Engineering and Design. 2020; 356: 110365 (13 pp.). https://doi.org/10.1016/j.nucengdes.2019.110365
DORA PSI
Rochman D, Koning AJ, Sublet J-C
A statistical analysis of evaluated neutron resonances with TARES for JEFF-3.3, JENDL-4.0, ENDF/B-VIII.0 and TENDL-2019
Nuclear Data Sheets. 2020; 163: 163-190. https://doi.org/10.1016/j.nds.2019.12.003
DORA PSI
Rochman D, Vasiliev A, Ferroukhi H, Seidl M, Basualdo J
Improvement of PIE analysis with a full core simulation: the U1 case

Annals of Nuclear Energy. 2020; 148: 107706 (11 pp.). https://doi.org/10.1016/j.anucene.2020.107706
DORA PSI
Rochman D, Dokhane A, Vasiliev A, Ferroukhi H, Hursin M
Nuclear data uncertainties for Swiss BWR spent nuclear fuel characteristics
European Physical Journal Plus. 2020; 135: 233 (18 pp.). https://doi.org/10.1140/epjp/s13360-020-00258-2
DORA PSI
Rochman D, Dokhane A, Vasiliev A, Ferroukhi H, Hursin M
Nuclear data uncertainties for core parameters based on Swiss BWR operated cycles
Annals of Nuclear Energy. 2020; 148: 107727 (8 pp.). https://doi.org/10.1016/j.anucene.2020.107727
DORA PSI
Rochman D, Vasiliev A, Ferroukhi H, Pecchia M
Optimization of Swiss used nuclear fuel canister for final repository: homogeneous vs. mixed loading
Annals of Nuclear Energy. 2020; 148: 107756 (8 pp.). https://doi.org/10.1016/j.anucene.2020.107756
DORA PSI
Sakellarakis VD, Vera-Tudela W, Doll U, Ebi D, Wright YM, Boulouchos K
The effect of high-pressure injection variations on the mixing state of underexpanded methane jets
International Journal of Engine Research. 2020; 22(9): 2900-2918. https://doi.org/10.1177/1468087420960895
DORA PSI
Scolaro A, Clifford I, Fiorina C, Pautz A
The OFFBEAT multi-dimensional fuel behavior solver
Nuclear Engineering and Design. 2020; 358: 110416 (16 pp.). https://doi.org/10.1016/j.nucengdes.2019.110416
DORA PSI
Shcherbanev S, Morinière T, Solana-Pérez R, Weilenmann M, Xiong Y, Doll U, et al.
Anchoring of premixed jet flames in vitiated crossflow with pulsed nanosecond spark discharge
Applications in Energy and Combustion Science. 2020; 1-4: 100010 (14 pp.). https://doi.org/10.1016/j.jaecs.2020.100010
DORA PSI
Siefman D, Hursin M, Perret G, Pautz A
Applying SHARK-X to perform data assimilation with the LWR-PROTEUS Phase II integral experiments
Progress in Nuclear Energy. 2020; 121: 103245 (9 pp.). https://doi.org/10.1016/j.pnucene.2020.103245
DORA PSI
Siefman D, Hursin M, Sjostrand H, Schnabel G, Rochman D, Pautz A
Data assimilation of post-irradiation examination data for fission yields from GEF
EPJ Nuclear Sciences and Technologies. 2020; 6: 52 (17 pp.). https://doi.org/10.1051/epjn/2020015
DORA PSI
Siefman D, Hursin M, Aufiero M, Bidaud A, Pautz A
On data assimilation with Monte-Carlo-calculated and statistically uncertain sensitivity coefficients
Annals of Nuclear Energy. 2020; 135: 106951 (13 pp.). https://doi.org/10.1016/j.anucene.2019.106951
DORA PSI
Solans V, Rochman D, Ferroukhi H, Vasiliev A, Pautz A
Loading optimization for Swiss used nuclear fuel assemblies into final disposal canisters
Nuclear Engineering and Design. 2020; 370: 110897 (11 pp.). https://doi.org/10.1016/j.nucengdes.2020.110897
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 2 - results of severe accident analyses for unit 2
Nuclear Engineering and Design. 2020; 369: 110840 (10 pp.). https://doi.org/10.1016/j.nucengdes.2020.110840
DORA PSI
Soubelet B, Adams R, Kromer H, Prasser H-M
Calibration technique and sample measurement database for material decomposition imaging using a compact deuterium-deuterium (D-D) fast neutron generator
Radiation Physics and Chemistry. 2020; 176: 108930 (18 pp.). https://doi.org/10.1016/j.radphyschem.2020.108930
DORA PSI
Vasiliev A, Grimm P, Ferroukhi H, Pecchia M, Ledergerber G
A comprehensive theoretical assessment of potential 'tramp uranium' isotopic evolution in BWR reactors
Annals of Nuclear Energy. 2020; 144: 107489 (11 pp.). https://doi.org/10.1016/j.anucene.2020.107489
DORA PSI
Vitullo F, Lamirand V, Mosset J-B, Frajtag P, Pakari O, Perret G, et al.
A mm³ fiber-coupled scintillator for in-core thermal neutron detection in CROCUS
IEEE Transactions on Nuclear Science. 2020; 67(4): 625-635. https://doi.org/10.1109/TNS.2020.2977530
DORA PSI
Vitullo F, Krepel J, Kalilainen J, Prasser H-M, Pautz A
Statistical burnup distribution of moving pebbles in the HTR-PM reactor
Journal of Nuclear Engineering and Radiation Science. 2020; 6(2): 021108 (14 pp.). https://doi.org/10.1115/1.4044910
DORA PSI
Wolfertz A, Adams R, Perret G
First tests of a gamma-blind fast neutron detector using a ZnS:Ag-epoxy mixture cast around wavelength-shifting fibers
Nuclear Instruments and Methods in Physics Research, Section A: Accelerators, Spectrometers, Detectors and Associated Equipment. 2020; 971: 164003 (9 pp.). https://doi.org/10.1016/j.nima.2020.164003
DORA PSI

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2019

Andreani M, Gaikwad AJ, Ganju S, Gera B, Grigoryev S, Herranz LE, et al.
Synthesis of a 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
Nuclear Engineering and Design. 2019; 354: 110177 (31 pp.). https://doi.org/10.1016/j.nucengdes.2019.110177
DORA PSI
Chionis D, Dokhane A, Ferroukhi H, Pautz A
Application of causality analysis on nuclear reactor systems
Chaos: An Interdisciplinary Journal of Nonlinear Science. 2019; 29(4): 043126 (16 pp.). https://doi.org/10.1063/1.5083905
DORA PSI
Clifford I, Pecchia M, Mukin R, Cozzo C, Ferroukhi H, Gorzel A
Studies on the effects of local power peaking on heat transfer under dryout conditions in BWRs
Annals of Nuclear Energy. 2019; 130: 440-451. https://doi.org/10.1016/j.anucene.2019.03.017
DORA PSI
Dehbi A, Kelm S, Kalilainen J, Mueller H
The influence of thermal radiation on the free convection inside enclosures
Nuclear Engineering and Design. 2019; 341: 176-185. https://doi.org/10.1016/j.nucengdes.2018.10.025
DORA PSI
Fernandez-Moguel L, Rydl A, Lind T
Updated analysis of Fukushima Unit 3 with MELCOR 2.1. Part 2: fission product release and transport analysis
Annals of Nuclear Energy. 2019; 130: 93-106. https://doi.org/10.1016/j.anucene.2019.02.017
DORA PSI
Fernandez-Moguel L, Rydl A, Lind T
Updated analysis of Fukushima unit 3 with MELCOR 2.1. Part 1: thermal-hydraulic analysis
Annals of Nuclear Energy. 2019; 123: 59-77. https://doi.org/10.1016/j.anucene.2018.09.008
DORA PSI
Gallego-Marcos I, Kudinov P, Villanueva W, Kapulla R, Paranjape S, Paladino D, et al.
Pool stratification and mixing induced by steam injection through spargers: CFD modelling of the PPOOLEX and PANDA experiments
Nuclear Engineering and Design. 2019; 347: 67-85. https://doi.org/10.1016/j.nucengdes.2019.03.011
DORA PSI
Griffin PJ, Koning AJ, Rochman D
Impact of nuclear data uncertainty in the modeling of neutron-induced recoil atom energy distributions in silicon
IEEE Transactions on Nuclear Science. 2019; 66(7): 1719-1729. https://doi.org/10.1109/TNS.2019.2894730
DORA PSI
Hennig D, Lange C, Rizwan-uddin, Dokhane A, Knospe A
Principles for the application of bifurcation theory for the systematic analysis of nuclear reactor stability, part1: theory
Progress in Nuclear Energy. 2019; 115: 231-249. https://doi.org/10.1016/j.pnucene.2019.02.009
DORA PSI
Hennig D, Rizwan-uddin, Lange C, Dokhane A, Knospe A
Principles for the application of bifurcation theory for the systematic analysis of nuclear reactor stability, part2: application
Progress in Nuclear Energy. 2019; 113: 263-280. https://doi.org/10.1016/j.pnucene.2019.01.009
DORA PSI
Kalilainen J, Lind T, Stuckert J, Bergfeldt T, Sippula O, Jokiniemi J
The measurement of Ag/In/Cd release under air-ingress conditions in the QUENCH-18 bundle test
Journal of Nuclear Materials. 2019; 517: 315-327. https://doi.org/10.1016/j.jnucmat.2019.02.021
DORA PSI
Koning AJ, Rochman D, Sublet J-C, Dzysiuk N, Fleming M, van der Marck S
TENDL: complete nuclear data library for innovative nuclear science and technology
Nuclear Data Sheets. 2019; 155: 1-55. https://doi.org/10.1016/j.nds.2019.01.002
DORA PSI
Kromer H, Adams R, Soubelet B, Zboray R, Prasser H-M
Thermal analysis, design, and testing of a rotating beam target for a compact D-D fast neutron generator
Applied Radiation and Isotopes. 2019; 145: 47-54. https://doi.org/10.1016/j.apradiso.2018.12.009
DORA PSI
Lind T, Guentay S, Herranz LE, Suckow D
A summary of the ARTIST: aerosol retention during SGTR severe accident
Annals of Nuclear Energy. 2019; 131: 385-400. https://doi.org/10.1016/j.anucene.2019.04.006
DORA PSI
Nikitin K, Mueller P, Bruder A, Walser S, Judd J, Hiltbrand D
BWR-4 ATWS modeling with RELAP5-S3K
Nuclear Engineering and Design. 2019; 344: 38-45. https://doi.org/10.1016/j.nucengdes.2019.01.023
DORA PSI
Papini D, Andreani M, Steiner P, Ničeno B, Klügel J-U, Prasser H-M
Evaluation of the PAR mitigation system in Swiss PWR containment using the GOTHIC code
Nuclear Technology. 2019; 205(1-2): 153-173. https://doi.org/10.1080/00295450.2018.1505356
DORA PSI
Paranjape S, Mignot G, Kapulla R, Paladino D
Experimental investigation of gas transport induced by containment spray activation during a scaled severe accident scenario
Nuclear Engineering and Design. 2019; 342: 88-98. https://doi.org/10.1016/j.nucengdes.2018.11.017
DORA PSI
Park J, Kim W, Hursin M, Perret G, Vasiliev A, Rochman D, et al.
Uncertainty quantification of LWR-PROTEUS Phase II experiments using CASMO-5
Annals of Nuclear Energy. 2019; 131: 9-22. https://doi.org/10.1016/j.anucene.2019.03.023
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
Annals of Nuclear Energy. 2019; 129: 67-78. https://doi.org/10.1016/j.anucene.2019.01.047
DORA PSI
Pelloni S, Rochman D
Enhancements along with application of the Asymptotic Progressing nuclear data Incremental Adjustment (APIA) methodology by individual assimilations of fast reactor data
Annals of Nuclear Energy. 2019; 129: 79-89. https://doi.org/10.1016/j.anucene.2019.01.057
DORA PSI
Perret G, Wicaksono D, Clifford ID, Ferroukhi H
Global sensitivity and registration strategy for temperature profile of reflood experiment simulations
Nuclear Technology. 2019; 205(12): 1638-1651. https://doi.org/10.1080/00295450.2019.1591154
DORA PSI
Rochman D, Vasiliev A, Ferroukhi H, Pelloni S, Bauge E, Koning A
Correlation ν̅ _p– σ for U-Pu in the thermal and resonance neutron range via integral information
European Physical Journal Plus. 2019; 134: 453 (12 pp.). https://doi.org/10.1140/epjp/i2019-12875-7
DORA PSI
Shama A, Pouchon MA, Clifford I
Simulation of the microfluidic mixing and the droplet generation for 3D printing of nuclear fuels
Additive Manufacturing. 2019; 26: 1-14. https://doi.org/10.1016/j.addma.2018.12.011
DORA PSI
Skorek T, de Crécy A, Kovtonyuk A, Petruzzi A, Mendizábal R, de Alfonso E, et al.
Quantification of the uncertainty of the physical models in the system thermal-hydraulic codes – PREMIUM benchmark
Nuclear Engineering and Design. 2019; 354: 110199 (23 pp.). https://doi.org/10.1016/j.nucengdes.2019.110199
DORA PSI
Soubelet B, Adams R, Kromer H, Zboray R, Prasser HM
Feasibility study of using a compact deuterium-deuterium (D-D) neutron generator for energy-selective transmission tomography
Radiation Physics and Chemistry. 2019; 156: 292-299. https://doi.org/10.1016/j.radphyschem.2018.11.017
DORA PSI
Sublet J-C, Bondarenko IP, Bonny G, Conlin JL, Gilbert MR, Greenwood LR, et al.
Neutron-induced damage simulations: beyond defect production cross-section, displacement per atom and iron-based metrics
European Physical Journal Plus. 2019; 134(7): 350 (50 pp.). https://doi.org/10.1140/epjp/i2019-12758-y
DORA PSI
Torres LA, Chionis D, Montalvo C, Dokhane A, García-Berrocal A
Neutron noise analysis of simulated mechanical and thermal-hydraulic perturbations in a PWR core
Annals of Nuclear Energy. 2019; 126: 242-252. https://doi.org/10.1016/j.anucene.2018.11.032
DORA PSI
Vasiliev A, Canepa S, Ferroukhi H, Boyarinov VF, Fomichenko PA, Joo HG, et al.
Cross-verification of SUHAM-TD and nTracer reactivity insertion transient solutions without materials homogenization approximation using OECD/NEA C5G7-TD benchmark
Annals of Nuclear Energy. 2019; 134: 235-243. https://doi.org/10.1016/j.anucene.2019.06.002
DORA PSI
Vasiliev A, Herrero J, Pecchia M, Rochman D, Ferroukhi H, Caruso S
Preliminary assessment of criticality safety constraints for swiss spent nuclear fuel loading in disposal canisters
Materials. 2019; 12(3): 494 (30 pp.). https://doi.org/10.3390/ma12030494
DORA PSI
Yang J, Suckow D, Lind T, Prasser H-M
Study of level swell for a Filtered Containment Venting System at the VEFITA facility
Progress in Nuclear Energy. 2019; 113: 7-17. https://doi.org/10.1016/j.pnucene.2019.01.003
DORA PSI

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2018

Albiol T, Herranz L, Riera E, Dalibart C, Lind T, Del Corno A, et al.
Main results of the European PASSAM project on severe accident source term mitigation
Annals of Nuclear Energy. 2018; 116: 42-56. https://doi.org/10.1016/j.anucene.2018.02.024
DORA PSI
Andreani M, Paladino D, Papini D
Multi-step planning calculations with the GOTHIC code used for the design of complex experiments in the PANDA facility
Nuclear Engineering and Design. 2018; 339: 116-125. https://doi.org/10.1016/j.nucengdes.2018.09.005
DORA PSI
Bauge E, Rochman DA
Cross-observables and cross-isotopes correlations in nuclear data from integral constraints
EPJ Nuclear Sciences and Technologies. 2018; 4: 35 (6 pp.). https://doi.org/10.1051/epjn/2018011
DORA PSI
Beghi I, Lind T, Prasser H-M
Experimental studies on retention of iodine in a wet scrubber
Nuclear Engineering and Design. 2018; 326: 234-243. https://doi.org/10.1016/j.nucengdes.2017.11.025
DORA PSI
Bousbia Salah A, Ceuca SC, Puragliesi R, Mukin R, Grahn A, Kliem S, et al.
Unsteady single-phase natural-circulation flow mixing prediction using 3-D thermal-hydraulic system and CFD Codes
Nuclear Technology. 2018; 203(3): 293-314. https://doi.org/10.1080/00295450.2018.1461517
DORA PSI
Brown DA, Chadwick MB, Capote R, Kahler AC, Trkov A, Herman MW, et al.
ENDF/B-VIII.0: the 8^th major release of the nuclear reaction data library with CIELO-project cross sections, new standards and thermal scattering data
Nuclear Data Sheets. 2018; 148: 1-142. https://doi.org/10.1016/j.nds.2018.02.001
DORA PSI
Clifford I, Pecchia M, Puragliesi R, Vasiliev A, Ferroukhi H
On the characteristics of the flow and heat transfer in the core bypass region of a PWR
Nuclear Engineering and Design. 2018; 330: 117-128. https://doi.org/10.1016/j.nucengdes.2018.01.039
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
Annals of Nuclear Energy. 2018; 120: 880-887. https://doi.org/10.1016/j.anucene.2018.06.043
DORA PSI
Cozzo C, Rahman S
SiC cladding thermal conductivity requirements for normal operation and LOCA conditions
Progress in Nuclear Energy. 2018; 106: 278-283. https://doi.org/10.1016/j.pnucene.2018.03.016
DORA PSI
Dokhane A, Grandi G, Vasiliev A, Rochman D, Ferroukhi H
Validation of PSI best estimate plus uncertainty methodology against SPERT-III reactivity initiated accident experiments
Annals of Nuclear Energy. 2018; 118: 178-184. https://doi.org/10.1016/j.anucene.2018.04.022
DORA PSI
Dupont J, Mignot G, Paladino D, Prasser H-M
Mid wave infrared thermography of water films in condensing and evaporating environments
Nuclear Engineering and Design. 2018; 336: 80-89. https://doi.org/10.1016/j.nucengdes.2017.06.027
DORA PSI
Dzysiuk N, Koning AJ, Rochman D, Fischer U
Improving activation cross sections for fusion applications
Fusion Science and Technology. 2018; 73(1): 13-24. https://doi.org/10.1080/15361055.2017.1372682
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
Fusion Engineering and Design. 2018; 136: 162-167. https://doi.org/10.1016/j.fusengdes.2018.01.036
DORA PSI
Gallego-Marcos I, Kudinov P, Villanueva W, Kapulla R, Paranjape S, Paladino D, et al.
Pool stratification and mixing induced by steam injection through spargers: analysis of the PPOOLEX and PANDA experiments
Nuclear Engineering and Design. 2018; 337: 300-316. https://doi.org/10.1016/j.nucengdes.2018.07.004
DORA PSI
Gouëllo M, Kalilainen J, Kärkelä T, Auvinen A
Contribution to the understanding of iodine transport under primary circuit conditions: Csi/Cd and Csi/Ag interactions in condensed phase
Nuclear Materials and Energy. 2018; 17: 259-268. https://doi.org/10.1016/j.nme.2018.11.011
DORA PSI
Halouane Y, Dehbi A
CFD simulation of hydrogen mitigation by a passive autocatalytic recombiner
Nuclear Engineering and Design. 2018; 330: 488-496. https://doi.org/10.1016/j.nucengdes.2018.01.018
DORA PSI
Hursin M, Weiss C, Frajtag P, Lamirand V, Perret G, Kavrigin P, et al.
Testing of a sCVD diamond detection system in the CROCUS reactor
European Physical Journal A: Hadrons and Nuclei. 2018; 54(5): 82 (11 pp.). https://doi.org/10.1140/epja/i2018-12519-1
DORA PSI
Jo Y, Hursin M, Lee D, Ferroukhi H, Pautz A
Analysis of simplified BWR full core with serpent-2/simulate-3 hybrid stochastic/deterministic code
Annals of Nuclear Energy. 2018; 111: 141-151. https://doi.org/10.1016/j.anucene.2017.08.061
DORA PSI
Kapulla R, Mignot G, Paranjape S, Andreani M, Paladino D
Large scale experiments representing a containment natural circulation loop during an accident scenario
Science and Technology of Nuclear Installations. 2018; 2018: 8989070 (12 pp.). https://doi.org/10.1155/2018/8989070
DORA PSI
Kapulla R, Uong D, Zimmer C, Paladino D
PIV measurements in the vicinity of a steam sparger in the PANDA facility
Nuclear Engineering and Design. 2018; 336: 112-121. https://doi.org/10.1016/j.nucengdes.2017.07.003
DORA PSI
Khvostov G
Modeling of central void formation in LWR fuel pellets due to high-temperature restructuring
Nuclear Engineering and Technology. 2018; 50(7): 1190-1197. https://doi.org/10.1016/j.net.2018.07.003
DORA PSI
Khvostov G
Models for numerical simulation of burst FGR in fuel rods under the conditions of RIA
Nuclear Engineering and Design. 2018; 328: 36-57. https://doi.org/10.1016/j.nucengdes.2017.12.028
DORA PSI
Kim H, Dehbi A, Kalilainen J
Measurements and LES computations of a turbulent particle-laden flow inside a cubical differentially heated cavity
Atmospheric Environment. 2018; 186: 216-228. https://doi.org/10.1016/j.atmosenv.2018.05.037
DORA PSI
Marelli E, Villevieille C, Park S, Hérault N, Marino C
Co-Free P2–Na_0.67Mn_0.6Fe_0.25Al_0.15O₂ as promising cathode material for sodium-ion batteries
ACS Applied Energy Materials. 2018; 1(11): 5960-5967. https://doi.org/10.1021/acsaem.8b01015
DORA PSI
Mignot G, Dupont J, Paranjape S, Ouldrebai H, Bissels W-M, Paladino D, et al.
Measurement of liquid films thickness in a condensing and re-evaporating environment using attenuation of near infrared light
Nuclear Engineering and Design. 2018; 336: 64-73. https://doi.org/10.1016/j.nucengdes.2017.06.023
DORA PSI
Mukin R, Clifford I, Zerkak O, Ferroukhi H
Modeling and analysis of selected organization for economic cooperation and development PKL-3 station blackout experiments using TRACE
Nuclear Engineering and Technology. 2018; 50(3): 356-367. https://doi.org/10.1016/j.net.2017.12.005
DORA PSI
Mukin R, Puragliesi R, Pecchia M, Seidl M
Subchannel modeling of single rod bowing in a bundle geometry
Nuclear Engineering and Design. 2018; 340: 347-369. https://doi.org/10.1016/j.nucengdes.2018.09.032
DORA PSI
Noguere G, Tommasi J, Privas E, Schmidt K-H, Rochman D
Systematics of Nd cumulative fission yields for neutron-induced fission of ²³⁵U, ²³⁸U, ²³⁸Pu, ²³⁹Pu, ²⁴⁰Pu and ²⁴¹Pu
European Physical Journal Plus. 2018; 133(3): 99 (14 pp.). https://doi.org/10.1140/epjp/i2018-11926-y
DORA PSI
Pakari O, Lamirand V, Perret G, Frajtag P, Pautz A
Kinetic parameter measurements in the CROCUS reactor using current mode instrumentation
IEEE Transactions on Nuclear Science. 2018; 65(9): 2456-2460. https://doi.org/10.1109/TNS.2018.2831180
DORA PSI
Papadionysiou M, Perret G, Zboray R, Adams R, Mosset J-B
Monte Carlo simulation of a scintillation detector for spent fuel characterization in a hot cell
Nuclear Engineering and Design. 2018; 332: 119-126. https://doi.org/10.1016/j.nucengdes.2018.03.033
DORA PSI
Pelloni S, Rochman D
Cross-section adjustment in the fast energy range on the basis of an Asymptotic Progressing nuclear data Incremental Adjustment (APIA) methodology
Annals of Nuclear Energy. 2018; 115: 323-342. https://doi.org/10.1016/j.anucene.2018.01.037
DORA PSI
Pelloni S, Rochman D
Performance assessment of adjusted nuclear data along with their covariances on the basis of fast reactor experiments
Annals of Nuclear Energy. 2018; 121: 361-373. https://doi.org/10.1016/j.anucene.2018.07.043
DORA PSI
Rahman S, Karanki DR, Epiney A, Wicaksono D, Zerkak O, Dang VN
Deterministic sampling for propagating epistemic and aleatory uncertainty in dynamic event tree analysis
Reliability Engineering and System Safety. 2018; 175: 62-78. https://doi.org/10.1016/j.ress.2018.03.009
DORA PSI
Rochman D, Vasiliev A, Ferroukhi H, Pecchia M
Consistent criticality and radiation studies of Swiss spent nuclear fuel: the CS₂M approach
Journal of Hazardous Materials. 2018; 357: 384-392. https://doi.org/10.1016/j.jhazmat.2018.05.041
DORA PSI
Rochman D, Vasiliev A, Ferroukhi H, Dokhane H, Koning A
How inelastic scattering stimulates nonlinear reactor core parameter behaviour
Annals of Nuclear Energy. 2018; 112: 236-244. https://doi.org/10.1016/j.anucene.2017.10.018
DORA PSI
Rochman D, Bauge E, Vasiliev A, Ferroukhi H, Pelloni S, Koning AJ, et al.
Monte Carlo nuclear data adjustment via integral information
European Physical Journal Plus. 2018; 133(12): 537. https://doi.org/10.1140/epjp/i2018-12361-x
DORA PSI
Rochman DA, Bauge E, Vasiliev A, Ferroukhi H, Perret G
Nuclear data correlation between different isotopes via integral information
EPJ Nuclear Sciences and Technologies. 2018; 4: 7 (10 pp.). https://doi.org/10.1051/epjn/2018006
DORA PSI
Rochman DA, Vasiliev A, Dokhane A, Ferroukhi H
Uncertainties for Swiss LWR spent nuclear fuels due to nuclear data
EPJ Nuclear Sciences and Technologies. 2018; 4: 6 (15 pp.). https://doi.org/10.1051/epjn/2018005
DORA PSI
Rýdl A, Fernandez-Moguel L, Lind T
Modeling of aerosol fission product scrubbing in experiments and in integral severe accident scenarios
Nuclear Technology. 2018; 205(5): 655-670. https://doi.org/10.1080/00295450.2018.1511213
DORA PSI
Siefman D, Hursin M, Rochman D, Pelloni S, Pautz A
Stochastic vs. sensitivity-based integral parameter and nuclear data adjustments
European Physical Journal Plus. 2018; 133(10): 429 (10 pp.). https://doi.org/10.1140/epjp/i2018-12303-8
DORA PSI
Simakov SP, Fischer U, Koning AJ, Konobeyev AY, Rochman DA
Iron NRT- and arc-displacement cross sections and their covariances
Nuclear Materials and Energy. 2018; 15: 244-248. https://doi.org/10.1016/j.nme.2018.05.006
DORA PSI
Sjöstrand H, Asquith N, Helgesson P, Rochman D, van der Marck S
Efficient use of Monte Carlo: the fast correlation coefficient
EPJ Nuclear Sciences and Technologies. 2018; 4: 15 (5 pp.). https://doi.org/10.1051/epjn/2018019
DORA PSI
Vasiliev A, Rochman D, Pecchia M, Ferroukhi H
On the options for incorporating nuclear data uncertainties in criticality safety assessments for LWR fuel
Annals of Nuclear Energy. 2018; 116: 57-68. https://doi.org/10.1016/j.anucene.2018.01.046
DORA PSI
Zboray R, Trtik P
800 fps neutron radiography of air-water two-phase flow
MethodsX. 2018; 5: 96-102. https://doi.org/10.1016/j.mex.2018.01.008
DORA PSI
Zboray R, Bolesch C, Prasser H-M
Development of neutron and X-ray imaging techniques for nuclear fuel bundle optimization
Nuclear Engineering and Design. 2018; 336: 24-33. https://doi.org/10.1016/j.nucengdes.2017.04.035
DORA PSI

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2017

Adams R, Zboray R
Gamma radiography and tomography with a CCD camera and Co-60 source
Applied Radiation and Isotopes. 2017; 127: 82-86. https://doi.org/10.1016/j.apradiso.2017.05.011
DORA PSI
Aures A, Bostelmann F, Hursin M, Leray O
Benchmarking and application of the state-of-the-art uncertainty analysis methods XSUSA and SHARK-X
Annals of Nuclear Energy. 2017; 101: 262-269. https://doi.org/10.1016/j.anucene.2016.11.025
DORA PSI
Bocharov D, Chollet M, Krack M, Bertsch J, Grolimund D, Martin M, et al.
Analysis of the U L₃-edge X-ray absorption spectra in UO₂ using molecular dynamics simulations
Progress in Nuclear Energy. 2017; 94: 187-193. https://doi.org/10.1016/j.pnucene.2016.07.017
DORA PSI
Bubelis E, Tosello A, Pfrang W, Schikorr M, Mikityuk K, Panadero A-L, et al.
System codes benchmarking on a low sodium void effect SFR heterogeneous core under ULOF conditions
Nuclear Engineering and Design. 2017; 320: 325-345. https://doi.org/10.1016/j.nucengdes.2017.06.015
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
EPJ Nuclear Sciences and Technologies. 2017; 3: 3 (5 pp.). https://doi.org/10.1051/epjn/2016040
DORA PSI
Dehbi A, Kalilainen J, Lind T, Auvinen A
A large eddy simulation of turbulent particle-laden flow inside a cubical differentially heated cavity
Journal of Aerosol Science. 2017; 103: 67-82. https://doi.org/10.1016/j.jaerosci.2016.10.003
DORA PSI
Dokhane A, Judd J, Gajev I, Zerkak O, Ferroukhi H, Kozlowski T
Analysis of Oskarshamn-2 stability event using TRACE/SIMULATE-3K and comparison to TRACE/PARCS and SIMULATE-3K stand-alone
Annals of Nuclear Energy. 2017; 102: 190-199. https://doi.org/10.1016/j.anucene.2016.12.015
DORA PSI
Fiorina C, Hursin M, Pautz A
Extension of the GeN-Foam neutronic solver to SP₃ analysis and application to the CROCUS experimental reactor
Annals of Nuclear Energy. 2017; 101: 419-428. https://doi.org/10.1016/j.anucene.2016.11.042
DORA PSI
Grimm P, Hursin M, Perret G, Siefman D, Ferroukhi H
Analysis of reactivity worths of burnt PWR fuel samples measured in LWR-PROTEUS Phase II using a CASMO-5 reflected-assembly model
Progress in Nuclear Energy. 2017; 101: 280-287. https://doi.org/10.1016/j.pnucene.2017.03.018
DORA PSI
Guo Z, Ngayam-Happy R, Krack M, Pautz A
Atomic-scale effects of chromium-doping on defect behaviour in uranium dioxide fuel
Journal of Nuclear Materials. 2017; 488: 160-172. https://doi.org/10.1016/j.jnucmat.2017.02.043
DORA PSI
Halouane Y, Dehbi A
CFD simulations of premixed hydrogen combustion using the Eddy Dissipation and the Turbulent Flame Closure models
International Journal of Hydrogen Energy. 2017; 42(34): 21990-22004. https://doi.org/10.1016/j.ijhydene.2017.07.075
DORA PSI
Helgesson P, Sjöstrand H, Koning AJ, Rydén J, Rochman D, Alhassan E, et al.
Combining Total Monte Carlo and Unified Monte Carlo: Bayesian nuclear data uncertainty quantification from auto-generated experimental covariances
Progress in Nuclear Energy. 2017; 96: 76-96. https://doi.org/10.1016/j.pnucene.2016.11.006
DORA PSI
Helgesson P, Sjöstrand H, Rochman D
Uncertainty-driven nuclear data evaluation including thermal (n,α) applied to ⁵⁹Ni
Nuclear Data Sheets. 2017; 145: 1-24. https://doi.org/10.1016/j.nds.2017.09.001
DORA PSI
Hursin M, Bogetic S, Dohkane A, Canepa S, Zerkak O, Ferroukhi H, et al.
Development and validation of a TRACE/PARCS core model of Leibstadt Kernkraftwerk cycle 19
Annals of Nuclear Energy. 2017; 101: 559-575. https://doi.org/10.1016/j.anucene.2016.11.001
DORA PSI
Karanki DR, Rahman S, Dang VN, Zerkak O
Epistemic and aleatory uncertainties in integrated deterministic and probabilistic safety assessment: tradeoff between accuracy and accident simulations
Reliability Engineering and System Safety. 2017; 162: 91-102. https://doi.org/10.1016/j.ress.2017.01.015
DORA PSI
Kelm S, Kapulla R, Allelein H-J
Erosion of a confined stratified layer by a vertical jet - detailed assessment of a CFD approach against the OECD/NEA PSI benchmark
Nuclear Engineering and Design. 2017; 312: 228-238. https://doi.org/10.1016/j.nucengdes.2016.09.014
DORA PSI
Kliem S, Kozmenkov Y, Hadek J, Perin Y, Fouquet F, Bernard F, et al.
Testing the NURESIM platform on a PWR main steam line break benchmark
Nuclear Engineering and Design. 2017; 321: 8-25. https://doi.org/10.1016/j.nucengdes.2017.05.028
DORA PSI
Kéri A, Dähn R, Krack M, Churakov SV
Combined XAFS spectroscopy and ab initio study on the characterization of iron incorporation by montmorillonite
Environmental Science and Technology. 2017; 51(18): 10585-10594. https://doi.org/10.1021/acs.est.7b01670
DORA PSI
Leray O, Ferroukhi H, Hursin M, Vasiliev A, Rochman D
Methodology for core analyses with nuclear data uncertainty quantification and application to Swiss PWR operated cycles
Annals of Nuclear Energy. 2017; 110: 547-559. https://doi.org/10.1016/j.anucene.2017.07.006
DORA PSI
Leray O, Fiorito L, Rochman D, Ferroukhi H, Stankovskiy A, Van den Eynde G
Uncertainty propagation of fission product yields to nuclide composition and decay heat for a PWR UO2 fuel assembly
Progress in Nuclear Energy. 2017; 101: 486-495. https://doi.org/10.1016/j.pnucene.2017.05.033
DORA PSI
Li J, Rochman D, Vasiliev A, Ferroukhi H, Herrero J, Pautz A, et al.
Bowing effects on isotopic concentrations for simplified PWR assemblies and full cores
Annals of Nuclear Energy. 2017; 110: 1023-1029. https://doi.org/10.1016/j.anucene.2017.08.022
DORA PSI
Li J, Rochman D, Herrero J, Vasiliev A, Ferroukhi H, Pautz A, et al.
UO₂ fuel pin bowing effects on isotopic concentrations
Annals of Nuclear Energy. 2017; 105: 361-368. https://doi.org/10.1016/j.anucene.2017.03.038
DORA PSI
Michel-Sendis F, Gauld I, Martinez JS, Alejano C, Bossant M, Boulanger D, et al.
SFCOMPO-2.0: an OECD NEA database of spent nuclear fuel isotopic assays, reactor design specifications, and operating data
Annals of Nuclear Energy. 2017; 110: 779-788. https://doi.org/10.1016/j.anucene.2017.07.022
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
Nuclear Engineering and Design. 2017; 312: 351-360. https://doi.org/10.1016/j.nucengdes.2016.12.012
DORA PSI
Pecchia M, Vasiliev A, Ferroukhi H, Pautz A
A methodology for evaluating weighting functions using MCNP and its application to PWR ex-core analyses
Annals of Nuclear Energy. 2017; 105: 121-132. https://doi.org/10.1016/j.anucene.2017.03.008
DORA PSI
Pelloni S
Comparison of progressive incremental adjustment sequences for cross-section and variance/covariance data adjustment by analyzing fast-spectrum systems
Annals of Nuclear Energy. 2017; 106: 33-50. https://doi.org/10.1016/j.anucene.2017.03.040
DORA PSI
Perret G, Geslot B, Gruel A, Blaise P, Di-Salvo J, De Izarra G, et al.
Kinetic parameter measurements in the Minerve reactor
IEEE Transactions on Nuclear Science. 2017; 64(1): 724-734. https://doi.org/10.1109/TNS.2016.2637569
DORA PSI
Rochman D, Bauge E, Vasiliev A, Ferroukhi H
Correlation ν̅_p - σ - χ in the fast neutron range via integral information
EPJ Nuclear Sciences and Technologies. 2017; 3: 14 (8 pp.). https://doi.org/10.1051/epjn/2017009
DORA PSI
Rochman D, Leray O, Hursin M, Ferroukhi H, Vasiliev A, Aures A, et al.
Nuclear data uncertainties for typical LWR fuel assemblies and a simple reactor core
Nuclear Data Sheets. 2017; 139: 1-76. https://doi.org/10.1016/j.nds.2017.01.001
DORA PSI
Rochman D, Goriely S, Koning AJ, Ferroukhi H
Radiative neutron capture: Hauser Feshbach vs. statistical resonances
Physics Letters, Section B: Nuclear, Elementary Particle and High-Energy Physics. 2017; 764: 109-113. https://doi.org/10.1016/j.physletb.2016.11.018
DORA PSI
Yin W, Krack M, Li X, Chen L, Liu L
Periodic continuum solvation model integrated with first-principles calculations for solid surfaces
Progress in Natural Science: Materials International. 2017; 27(2): 283-288. https://doi.org/10.1016/j.pnsc.2017.03.003
DORA PSI
Zboray R, Adams R, Kis Z
Fast neutron radiography and tomography at a 10 MW research reactor beamline
Applied Radiation and Isotopes. 2017; 119: 43-50. https://doi.org/10.1016/j.apradiso.2016.10.012
DORA PSI

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2016

Adams R, Zboray R, Prasser H-M
A novel fast-neutron tomography system based on a plastic scintillator array and a compact D-D neutron generator
Applied Radiation and Isotopes. 2016; 107: 1-7. https://doi.org/10.1016/j.apradiso.2015.09.002
DORA PSI
Adorni M, Herranz LE, Hollands T, Ahn K-II, Bals C, D'Auria F, et al.
OECD/NEA Sandia Fuel Project phase I: benchmark of the ignition testing
Nuclear Engineering and Design. 2016; 307: 418-430. https://doi.org/10.1016/j.nucengdes.2016.07.016
DORA PSI
Alhassan E, Sjöstrand H, Helgesson P, Österlund M, Pomp S, Koning AJ, et al.
On the use of integral experiments for uncertainty reduction of reactor macroscopic parameters within the TMC methodology
Progress in Nuclear Energy. 2016; 88: 43-52. https://doi.org/10.1016/j.pnucene.2015.11.015
DORA PSI
Alhassan E, Sjöstrand H, Helgesson P, Österlund M, Pomp S, Koning AJ, et al.
Selecting benchmarks for reactor simulations: an application to a lead fast reactor
Annals of Nuclear Energy. 2016; 96: 158-169. https://doi.org/10.1016/j.anucene.2016.05.033
DORA PSI
Andreani M, Badillo A, Kapulla R
Synthesis of the OECD/NEA-PSI CFD benchmark exercise
Nuclear Engineering and Design. 2016; 299: 59-80. https://doi.org/10.1016/j.nucengdes.2015.12.029
DORA PSI
Beuzet E, Haurais F, Bals C, Coindreau O, Fernandez-Moguel L, Vasiliev A, et al.
Cladding oxidation during air ingress. Part II: synthesis of modelling results
Annals of Nuclear Energy. 2016; 93: 18-27. https://doi.org/10.1016/j.anucene.2015.12.031
DORA PSI
Bozzetti C, Daellenbach KR, Hueglin C, Fermo P, Sciare J, Kasper-Giebl A, et al.
Size-resolved identification, characterization, and quantification of primary biological organic aerosol at a European rural site
Environmental Science and Technology. 2016; 50(7): 3425-3434. https://doi.org/10.1021/acs.est.5b05960
DORA PSI
Brankov V, Khvostov G, Mikityuk K, Pautz A, Restani R, Abolhassani S, et al.
Analysis of effects of pellet-cladding bonding on trapping of the released fission gases in high burnup KKL BWR fuels
Nuclear Engineering and Design. 2016; 305: 559-568. https://doi.org/10.1016/j.nucengdes.2016.06.021
DORA PSI
Brankov V, Khvostov G, Mikityuk K, Pautz A, Wiesenack W
Characterization of the relocated and dispersed fuel in the Halden reactor project LOCA tests based on gamma scan data
Nuclear Engineering and Design. 2016; 300: 97-106. https://doi.org/10.1016/j.nucengdes.2015.11.023
DORA PSI
Cozzo C, Ishizaki K, Pouchon MA, Vaucher S
Developing an in situ EXAFS experiment of microwave-induced gelation
Journal of Sol-Gel Science and Technology. 2016; 78(3): 507-513. https://doi.org/10.1007/s10971-016-3992-5
DORA PSI
Daellenbach KR, Bozzetti C, Křepelová A, Canonaco F, Wolf R, Zotter P, et al.
Characterization and source apportionment of organic aerosol using offline aerosol mass spectrometry
Atmospheric Measurement Techniques. 2016; 9(1): 23-39. https://doi.org/10.5194/amt-9-23-2016
DORA PSI
Degueldre C, Fiorina C
The proto-Earth geo-reactor: reassessing the hypotheses
Solid Earth Sciences. 2016; 1(2): 49-63. https://doi.org/10.1016/j.sesci.2016.08.002
DORA PSI
Dehbi A
A unified correlation for steam condensation rates in the presence of air-helium mixtures under naturally driven flows
Nuclear Engineering and Design. 2016; 300: 601-609. https://doi.org/10.1016/j.nucengdes.2016.02.009
DORA PSI
Dehbi A, Suckow D, Lind T, Guentay S, Danner S, Mukin R
Key findings from the artist project on aerosol retention in a dry steam generator
Nuclear Engineering and Technology. 2016; 48(4): 870-880. https://doi.org/10.1016/j.net.2016.06.001
DORA PSI
Dokhane A, Ferroukhi H, Pautz A
Validation studies and interpretation of the Oskarshamn-2 1999 stability event with SIMULATE-3K
Annals of Nuclear Energy. 2016; 96: 344-353. https://doi.org/10.1016/j.anucene.2016.06.016
DORA PSI
Dupont J, Mignot G, Zboray R, Prasser H-M
Infrared film thickness measurement: comparison with cold neutron imaging
Journal of Nuclear Science and Technology. 2016; 53(5): 673-681. https://doi.org/10.1080/00223131.2015.1102779
DORA PSI
Epiney A, Canepa S, Zerkak O, Ferroukhi H
Towards a consolidated approach for the assessment of evaluation models of nuclear power reactors
Nuclear Technology. 2016; 196(2): 223-237. https://doi.org/10.13182/NT16-47
DORA PSI
Fiorina C, Kerkar N, Mikityuk K, Rubiolo P, Pautz A
Development and verification of the neutron diffusion solver for the GeN-Foam multi-physics platform
Annals of Nuclear Energy. 2016; 96: 212-222. https://doi.org/10.1016/j.anucene.2016.05.023
DORA PSI
Froidevaux P, Bochud F, Baechler S, Castella V, Augsburger M, Bailat C, et al.
²¹⁰Po poisoning as possible cause of death: forensic investigations and toxicological analysis of the remains of Yasser Arafat
Forensic Science International. 2016; 259: 1-9. https://doi.org/10.1016/j.forsciint.2015.09.019
DORA PSI
Helgesson P, Sjöstrand H, Koning AJ, Rydén J, Rochman D, Alhassan E, et al.
Sampling of systematic errors to estimate likelihood weights in nuclear data uncertainty propagation
Nuclear Instruments and Methods in Physics Research, Section A: Accelerators, Spectrometers, Detectors and Associated Equipment. 2016; 807: 137-149. https://doi.org/10.1016/j.nima.2015.10.024
DORA PSI
Herrero JJ, Vasiliev A, Pecchia M, Ferroukhi H, Caruso S
Review calculations for the OECD/NEA Burn-up Credit Criticality Safety Benchmark
Annals of Nuclear Energy. 2016; 87(P2): 48-57. https://doi.org/10.1016/j.anucene.2015.08.014
DORA PSI
Hursin M, Downar TJ, Yoon JI, Joo HG
Assessment of assembly homogenized two-steps core dynamic calculations using direct whole core transport solutions
Annals of Nuclear Energy. 2016; 87: 356-365. https://doi.org/10.1016/j.anucene.2015.09.015
DORA PSI
Hursin M, Scriven M, Perret G, Pautz A
Uncertainty quantification and representativity analysis of LWR-PROTEUS Phase III experiments using SHARKX
Annals of Nuclear Energy. 2016; 91: 48-58. https://doi.org/10.1016/j.anucene.2015.12.035
DORA PSI
Jayaraju ST, Roelofs F, Komen EMJ, Dehbi A
RANS modeling of fluid flow and dust deposition in nuclear pebble-beds
Nuclear Engineering and Design. 2016; 308: 222-237. https://doi.org/10.1016/j.nucengdes.2016.08.037
DORA PSI
Jäckel BS, Bevilacqua A, Ducros G, Gauntt R, Stuckert J
Land contamination activity data interpretation from Fukushima Daiichi accident
Nuclear Engineering and Design. 2016; 300: 28-33. https://doi.org/10.1016/j.nucengdes.2015.12.030
DORA PSI
Kalilainen J, Rantanen P, Lind T, Auvinen A, Dehbi A
Experimental investigation of a turbulent particle-laden flow inside a cubical differentially heated cavity
Journal of Aerosol Science. 2016; 100: 73-87. https://doi.org/10.1016/j.jaerosci.2016.06.001
DORA PSI
Khvostov G, Wiesenack W
Analysis of selected Halden overpressure tests using the FALCON code
Nuclear Engineering and Design. 2016; 310: 395-409. https://doi.org/10.1016/j.nucengdes.2016.10.033
DORA PSI
Leray O, Rochman D, Grimm P, Ferroukhi H, Vasiliev A, Hursin M, et al.
Nuclear data uncertainty propagation on spent fuel nuclide compositions
Annals of Nuclear Energy. 2016; 94: 603-611. https://doi.org/10.1016/j.anucene.2016.03.023
DORA PSI
Lindley BA, Fiorina C, Gregg R, Franceschini F, Parks GT
The effectiveness of full actinide recycle as a nuclear waste management strategy when implemented over a limited timeframe – Part II: thorium fuel cycle
Progress in Nuclear Energy. 2016; 87: 144-155. https://doi.org/10.1016/j.pnucene.2014.11.016
DORA PSI
Mignot G, Paranjape S, Paladino D, Jaeckel B, Rydl A
Large scale experiments simulating hydrogen distribution in a spent fuel pool building during a hypothetical fuel uncovery accident scenario
Nuclear Engineering and Technology. 2016; 48(4): 881-892. https://doi.org/10.1016/j.net.2016.06.005
DORA PSI
Mukin RV
Bubble reconstruction method for wire-mesh sensors measurements
Experiments in Fluids. 2016; 57(8): 133 (12 pp.). https://doi.org/10.1007/s00348-016-2220-y
DORA PSI
Mukin R, Dehbi A
Particle deposition modeling in the secondary side of a steam generator bundle model
Nuclear Engineering and Design. 2016; 299: 112-123. https://doi.org/10.1016/j.nucengdes.2015.09.001
DORA PSI
Paladino D, Andreani M, Guentay S, Mignot G, Kapulla R, Paranjape S, et al.
Outcomes from the EURATOM–ROSATOM ERCOSAM SAMARA projects on containment thermal-hydraulics for severe accident management
Nuclear Engineering and Design. 2016; 308: 103-114. https://doi.org/10.1016/j.nucengdes.2016.08.011
DORA PSI
Pecchia M, Wicaksono D, Grimm P, Vasiliev A, Perret G, Ferroukhi H, et al.
Validation of Monte Carlo based burnup codes against LWR-PROTEUS Phase-II experimental data
Annals of Nuclear Energy. 2016; 97: 153-164. https://doi.org/10.1016/j.anucene.2016.07.001
DORA PSI
Pellegrini M, Dolganov K, Herranz LE, Bonneville H, Luxat D, Sonnenkalb M, et al.
Benchmark study of the accident at the Fukushima Daiichi NPS: best-estimate case comparison
Nuclear Technology. 2016; 196(2): 198-210. https://doi.org/10.13182/NT16-63
DORA PSI
Perret G, Blaise P, Messaoudi N, Geslot B, Wagemans J, Baeten P, et al.
Validation of Monte-Carlo methods for generation time and delayed neutron fraction predictions
Annals of Nuclear Energy. 2016; 97: 165-170. https://doi.org/10.1016/j.anucene.2016.07.015
DORA PSI
Prasser H-M, Bolesch C, Cramer K, Ito D, Papadopoulos P, Saxena A, et al.
Bubbly, slug, and annular two-phase flow in tight-lattice subchannels
Nuclear Engineering and Technology. 2016; 48(4): 847-858. https://doi.org/10.1016/j.net.2016.06.007
DORA PSI
Puragliesi R, Zhou L, Zerkak O, Pautz A
Steady-state CFD simulations of an EPR^TM reactor pressure vessel: a validation study based on the JULIETTE experiments
Nuclear Engineering and Design. 2016; 300: 41-56. https://doi.org/10.1016/j.nucengdes.2015.12.025
DORA PSI
Rabiti C, Alfonsi A, Epiney A
New simulation schemes and capabilities for the PHISICS/RELAP5-3D coupled suite
Nuclear Science and Engineering. 2016; 182(1): 104-118. https://doi.org/10.13182/NSE14-143
DORA PSI
Rochman D, Leray O, Vasiliev A, Ferroukhi H, Koning AJ, Fleming M, et al.
A Bayesian Monte Carlo method for fission yield covariance information
Annals of Nuclear Energy. 2016; 95: 125-134. https://doi.org/10.1016/j.anucene.2016.05.005
DORA PSI
Rochman D, Vasiliev A, Ferroukhi H, Zhu T, van der Marck SC, Koning AJ
Nuclear data uncertainty for criticality-safety: Monte Carlo vs. linear perturbation
Annals of Nuclear Energy. 2016; 92: 150-160. https://doi.org/10.1016/j.anucene.2016.01.042
DORA PSI
Rochman D, Leray O, Perret G, Vasiliev A, Ferroukhi H, Koning AJ
Re-evaluation of the thermal neutron capture cross section of ¹⁴⁷Nd
Annals of Nuclear Energy. 2016; 94: 612-617. https://doi.org/10.1016/j.anucene.2016.03.024
DORA PSI
Rýdl A, Lind T, Birchley J
Integral analyses of fission product retention at mitigated thermally-induced SGTR using ARTIST experimental data
Nuclear Engineering and Design. 2016; 297: 175-187. https://doi.org/10.1016/j.nucengdes.2015.11.014
DORA PSI
Saxena A, Zboray R, Prasser H-M
Simulations and measurements of adiabatic annular flows in triangular, tight lattice nuclear fuel bundle model
Nuclear Engineering and Design. 2016; 299: 163-173. https://doi.org/10.1016/j.nucengdes.2015.07.063
DORA PSI
Stirling A, Rozgonyi T, Krack M, Bernasconi M
Prebiotic NH₃ formation: insights from simulations
Inorganic Chemistry. 2016; 55(4): 1934-1939. https://doi.org/10.1021/acs.inorgchem.5b02911
DORA PSI
Vasiliev A, Rochman DI, Pecchia M, Ferroukhi H
Exploring stochastic sampling in nuclear data uncertainties assessment for reactor physics applications and validation studies
Energies. 2016; 9(12): 1039 (18 pp.). https://doi.org/10.3390/en9121039
DORA PSI
Vasiliev A, Ferroukhi H, Pecchia M, Pautz A
Localized neutron flux assessment and verification studies using MCNPX PWR full core model
Annals of Nuclear Energy. 2016; 92: 317-332. https://doi.org/10.1016/j.anucene.2016.01.026
DORA PSI
Wicaksono D, Zerkak O, Pautz A
Global sensitivity analysis of transient code output applied to a reflood experiment model using the TRACE code
Nuclear Science and Engineering. 2016; 184(3): 400-429. https://doi.org/10.13182/NSE16-37
DORA PSI
Yin W-J, Wen B, Bandaru S, Krack M, Lau MW, Liu L-M
The effect of excess electron and hole on CO₂ adsorption and activation on rutile (110) surface
Scientific Reports. 2016; 6: 23298 (9 pp.). https://doi.org/10.1038/srep23298
DORA PSI
Zhang Y, Mikityuk K
Static and transient analysis of a medium-sized sodium cooled fast reactor loaded with oxide, nitride, carbide and metallic fuels
Annals of Nuclear Energy. 2016; 87: 761-771. https://doi.org/10.1016/j.anucene.2015.03.025
DORA PSI
Zhu T, Vasiliev A, Ferroukhi H, Rochman D, Pautz A
Testing the sampling-based NUSS-RF tool for the nuclear data-related global sensitivity analysis with Monte Carlo neutronics calculations
Nuclear Science and Engineering. 2016; 184(1): 69-83. https://doi.org/10.13182/NSE14-142
DORA PSI

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2015

Adams R, Bort L, Zboray R, Prasser H-M
Development and characterization of a D-D fast neutron generator for imaging applications
Applied Radiation and Isotopes. 2015; 96: 114-121. https://doi.org/10.1016/j.apradiso.2014.11.017
DORA PSI
Aufiero M, Bidaud A, Hursin M, Leppänen J, Palmiotti G, Pelloni S, et al.
A collision history-based approach to sensitivity/perturbation calculations in the continuous energy Monte Carlo code SERPENT
Annals of Nuclear Energy. 2015; 85: 245-258. https://doi.org/10.1016/j.anucene.2015.05.008
DORA PSI
Becker H, Bison G, Blau B, Chowdhuri Z, Eikenberg J, Fertl M, et al.
Neutron production and thermal moderation at the PSI UCN source
Nuclear Instruments and Methods in Physics Research, Section A: Accelerators, Spectrometers, Detectors and Associated Equipment. 2015; 777: 20-27. https://doi.org/10.1016/j.nima.2014.12.091
DORA PSI
Bertolus M, Freyss M, Dorado B, Martin G, Hoang K, Maillard S, et al.
Linking atomic and mesoscopic scales for the modelling of the transport properties of uranium dioxide under irradiation
Journal of Nuclear Materials. 2015; 462: 475-495. https://doi.org/10.1016/j.jnucmat.2015.02.026
DORA PSI
Bosshard C, Deville MO, Dehbi A, Leriche E
UDNS or LES, that is the question
Open Journal of Fluid Dynamics. 2015; 5(4): 339-352. https://doi.org/10.4236/ojfd.2015.54034
DORA PSI
Dangendorf V, Zboray R
Potential and status in imaging with fast neutrons
Neutron News. 2015; 26(2): 27-30. https://doi.org/10.1080/10448632.2015.1028276
DORA PSI
Dehbi A
A generalized correlation for steam condensation rates in the presence of air under turbulent free convection
International Journal of Heat and Mass Transfer. 2015; 86: 11754 (15 pp.). https://doi.org/10.1016/j.ijheatmasstransfer.2015.02.034
DORA PSI
Demeshko M, Dokhane A, Washio T, Ferroukhi H, Kawahara Y, Aguirre C
Application of continuous and structural ARMA modeling for noise analysis of a BWR coupled core and plant instability event
Annals of Nuclear Energy. 2015; 75: 645-657. https://doi.org/10.1016/j.anucene.2014.08.045
DORA PSI
Dupont J, Mignot G, Prasser H-M
Two-dimensional mapping of falling water film thickness with near-infrared attenuation
Experiments in Fluids. 2015; 56(5): 90 (16 pp.). https://doi.org/10.1007/s00348-015-1955-1
DORA PSI
Dupré A, Vasiliev A, Ferroukhi H, Pautz A
Towards modeling and validation enhancements of the PSI MCNPX fast neutron fluence computational scheme based on recent PWR experimental data
Annals of Nuclear Energy. 2015; 85: 820-829. https://doi.org/10.1016/j.anucene.2015.06.040
DORA PSI
Fernandez-Moguel L, Birchley J
Analysis of the accident in the Fukushima Daiichi nuclear power station unit 3 with MELCOR_2.1
Annals of Nuclear Energy. 2015; 83: 193-215. https://doi.org/10.1016/j.anucene.2015.04.021
DORA PSI
Fernandez-Moguel L
Comparative assessment of PSI air oxidation model implementation in SCDAPSim3.5, MELCOR 1.8.6 and MELCOR 2.1
Annals of Nuclear Energy. 2015; 81: 134-142. https://doi.org/10.1016/j.anucene.2015.03.015
DORA PSI
Fiorina C, Clifford I, Aufiero M, Mikityuk K
GeN-Foam: A novel OpenFOAM^® based multi-physics solver for 2D/3D transient analysis of nuclear reactors
Nuclear Engineering and Design. 2015; 294: 24-37. https://doi.org/10.1016/j.nucengdes.2015.05.035
DORA PSI
Freixa J, Martínez-Quiroga V, Zerkak O, Reventós F
Modelling guidelines for core exit temperature simulations with system codes
Nuclear Engineering and Design. 2015; 286: 116-129. https://doi.org/10.1016/j.nucengdes.2015.02.003
DORA PSI
Hombourger BA, Křepel J, Mikityuk K, Pautz A
Parametric lattice study of a graphite-moderated molten salt reactor
Journal of Nuclear Engineering and Radiation Science. 2015; 1(1): 011009 (8 pp.). https://doi.org/10.1115/1.4026401
DORA PSI
Hursin M, Perret G, Pautz A
Verification of the new implementations in SHARKX against TSUNAMI to perform pinpower UQ and representativity analysis
Annals of Nuclear Energy. 2015; 77: 300-309. https://doi.org/10.1016/j.anucene.2014.11.019
DORA PSI
Jayaraju ST, Sathiah P, Roelofs F, Dehbi A
RANS modeling for particle transport and deposition in turbulent duct flows: near wall model uncertainties
Nuclear Engineering and Design. 2015; 289: 60-72. https://doi.org/10.1016/j.nucengdes.2015.04.011
DORA PSI
Jäckel BS
Status of the spent fuel in the reactor buildings of Fukushima Daiichi 1-4
Nuclear Engineering and Design. 2015; 283: 2-7. https://doi.org/10.1016/j.nucengdes.2014.07.007
DORA PSI
Karanki DR, Kim T-W, Dang VN
A dynamic event tree informed approach to probabilistic accident sequence modeling: dynamics and variabilities in medium LOCA
Reliability Engineering and System Safety. 2015; 142: 78-91. https://doi.org/10.1016/j.ress.2015.04.011
DORA PSI
Krack M
On the ground state electronic structure of uranium dioxide
Physica Scripta. 2015; 90(9): 094014 (7 pp.). https://doi.org/10.1088/0031-8949/90/9/094014
DORA PSI
Lindley BA, Fiorina C, Gregg R, Franceschini F, Parks GT
The effectiveness of full actinide recycle as a nuclear waste management strategy when implemented over a limited timeframe - part I: uranium fuel cycle
Progress in Nuclear Energy. 2015; 85: 498-510. https://doi.org/10.1016/j.pnucene.2015.07.020
DORA PSI
Modin A, Suzuki M-T, Vegelius J, Yun Y, Shuh DK, Werme L, et al.
5 f-shell correlation effects in dioxides of light actinides studied by O 1s x-ray absorption and emission spectroscopies and first-principles calculations
Journal of Physics: Condensed Matter. 2015; 27(31): 315503 (8 pp.). https://doi.org/10.1088/0953-8984/27/31/315503
DORA PSI
Ngayam-Happy R, Krack M, Pautz A
Effects of stoichiometry on the defect clustering in uranium dioxide
Journal of Physics: Condensed Matter. 2015; 27(45): 455401 (13 pp.). https://doi.org/10.1088/0953-8984/27/45/455401
DORA PSI
Nikitin E, Fridman E, Mikityuk K
On the use of the SPH method in nodal diffusion analyses of SFR cores
Annals of Nuclear Energy. 2015; 85: 544-551. https://doi.org/10.1016/j.anucene.2015.06.007
DORA PSI
Nikitin E, Fridman E, Mikityuk K
Solution of the OECD/NEA neutronic SFR benchmark with Serpent-DYN3D and Serpent-PARCS code systems
Annals of Nuclear Energy. 2015; 75: 492-497. https://doi.org/10.1016/j.anucene.2014.08.054
DORA PSI
Pecchia M, Vasiliev A, Leray O, Ferroukhi H, Pautz A
Advanced calculation methodology for manufacturing and technological parameters' uncertainties propagation at arbitrary level of lattice elements grouping
Journal of Nuclear Science and Technology. 2015; 52(7-8): 1084-1092. https://doi.org/10.1080/00223131.2015.1032382
DORA PSI
Pecchia M, Parisi C, D'Auria F, Mazzantini O
Application of MCNP for predicting power excursion during LOCA in Atucha-2 PHWR
Annals of Nuclear Energy. 2015; 85: 271-278. https://doi.org/10.1016/j.anucene.2015.05.023
DORA PSI
Pecchia M, Vasiliev A, Ferroukhi H, Pautz A
Criticality safety evaluation of a Swiss wet storage pool using a global uncertainty analysis methodology
Annals of Nuclear Energy. 2015; 83: 226-235. https://doi.org/10.1016/j.anucene.2015.03.052
DORA PSI
Perkó Z, Pelloni S, Mikityuk K, Křepel J, Szieberth M, Gaëtan G, et al.
Core neutronics characterization of the GFR2400 gas cooled fast reactor
Progress in Nuclear Energy. 2015; 83: 460-481. https://doi.org/10.1016/j.pnucene.2014.09.016
DORA PSI
Rais A, Siefman D, Girardin G, Hursin M, Pautz A
Methods and models for the coupled neutronics and thermal-hydraulics analysis of the CROCUS reactor at EFPL
Science and Technology of Nuclear Installations. 2015; 2015: 237646 (9 pp.). https://doi.org/10.1155/2015/237646
DORA PSI
Ribeiro F, Khvostov G
Multi-scale approach to advanced fuel modelling for enhanced safety
Progress in Nuclear Energy. 2015; 84: 24-35. https://doi.org/10.1016/j.pnucene.2015.03.022
DORA PSI
Rochman D, Koning AJ, van der Marck SC
Improving neutronics simulations and uncertainties via a selection of nuclear data
European Physical Journal A: Hadrons and Nuclei. 2015; 51(12): 182 (11 pp.). https://doi.org/10.1140/epja/i2015-15182-0
DORA PSI
Salazar G, Zhang YL, Agrios K, Szidat S
Development of a method for fast and automatic radiocarbon measurement of aerosol samples by online coupling of an elemental analyzer with a MICADAS AMS
Nuclear Instruments and Methods in Physics Research, Section B: Beam Interactions with Materials and Atoms. 2015; 361: 163-167. https://doi.org/10.1016/j.nimb.2015.03.051
DORA PSI
Siefman DJ, Girardin G, Rais A, Pautz A, Hursin M
Full core modeling techniques for research reactors with irregular geometries using Serpent and PARCS applied to the CROCUS reactor
Annals of Nuclear Energy. 2015; 85: 434-443. https://doi.org/10.1016/j.anucene.2015.05.004
DORA PSI
Stirling A, Rozgonyi T, Krack M, Bernasconi M
Pyrite in contact with supercritical water: the desolation of steam
Physical Chemistry Chemical Physics. 2015; 17(26): 17375-17379. https://doi.org/10.1039/c5cp01146a
DORA PSI
Yang J, Lim J, Choi SW, Lee DY, Rassame S, Hibiki T, et al.
Behaviors of passive safety systems under a feed water line break LOCA on a generation III + boiling water reactor
Progress in Nuclear Energy. 2015; 83: 35-42. https://doi.org/10.1016/j.pnucene.2015.02.011
DORA PSI
Yin W-J, Krack M, Wen B, Ma S-Y, Liu L-M
CO₂ capture and conversion on rutile TiO₂(110) in the water environment: insight by first-principles calculations
Journal of Physical Chemistry Letters. 2015; 6(13): 2538-2545. https://doi.org/10.1021/acs.jpclett.5b00798
DORA PSI
Zanetti M, Cammi A, Fiorina C, Luzzi L
A Geometric Multiscale modelling approach to the analysis of MSR plant dynamics
Progress in Nuclear Energy. 2015; 83: 82-98. https://doi.org/10.1016/j.pnucene.2015.02.014
DORA PSI
Zboray R, Mignot G, Kapulla R, Paladino D
Erosion and break-up of light-gas layers by a horizontal jet in a multi-vessel, large-scale containment test system
Nuclear Engineering and Design. 2015; 291: 10-18. https://doi.org/10.1016/j.nucengdes.2015.05.006
DORA PSI
Zboray R, Dangendorf V, Mor I, Bromberger B, Tittelmeier K
Time-resolved fast-neutron radiography of air-water two-phase flows in a rectangular channel by an improved detection system
Review of Scientific Instruments. 2015; 86(7): 075103 (10 pp.). https://doi.org/10.1063/1.4926999
DORA PSI
Zerkak O, Kozlowski T, Gajev I
Review of multi-physics temporal coupling methods for analysis of nuclear reactors
Annals of Nuclear Energy. 2015; 84: 225-233. https://doi.org/10.1016/j.anucene.2015.01.019
DORA PSI
Zhu T, Vasiliev A, Ferroukhi H, Pautz A, Tarantola S
NUSS-RF: stochastic sampling-based tool for nuclear data sensitivity and uncertainty quantification
Journal of Nuclear Science and Technology. 2015; 52(7-8): 1000-1007. https://doi.org/10.1080/00223131.2015.1040864
DORA PSI
Zhu T, Vasiliev A, Ferroukhi H, Pautz A
NUSS: a tool for propagating multigroup nuclear data covariances in pointwise ACE-formatted nuclear data using stochastic sampling method
Annals of Nuclear Energy. 2015; 75: 713-722. https://doi.org/10.1016/j.anucene.2014.09.013
DORA PSI

Time-Resolved Fast Neutron Radiography Of Air-Water Two-Phase Flows
R Zboray, V Dangendorf, I Mor, B Bromberger, K Tittelmeier, H-M Prasser
Physics Procedia 69, 551 (2015).
http://dx.doi.org/10.1016/j.phpro.2015.07.078

Boron Dilution Transient Simulation Analyses In A Pwr With Neutronics/Thermal-Hydraulics Coupled Codes In The Nurisp Project
G. Jimenez, J.J. Herrero, A. Gommlich, S. Kliem, D. Cuervo, J. Jimenez
Annals of Nuclear Energy Vol. 84, Pp. 86-97 (2015)

Advanced Calculation Methodology For Manufacturing And Technological Parameters’ Uncertainties Propagation At Arbitrary Level Of Lattice Elements Grouping
M. Pecchia, A.Vasiliev, O.Leray, H.Ferroukhi, A.Pautz
Journal of Nuclear Science And Technology, Vol. 52:7-8, Pp. 1084-1092, (2015)

Comparative assesment of PSI Air oxidation model implementation in SCDAPSim 3.5, MELCOR 1.8.6 and MELCOR 2.1
L. Fernandez-Moguel
Annals of Nuclear Energy 81, 134
http://dx.doi.org/10.1016/j.anucene.2015.03.015

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2010 - 2014

Adams R, Zboray R, Cortesi M, Prasser H-M
Conceptual design and optimization of a plastic scintillator array for 2D tomography using a compact D-D fast neutron generator
Applied Radiation and Isotopes. 2014; 86: 63-70. https://doi.org/10.1016/j.apradiso.2014.01.001
DORA PSI
Bosshard C, Dehbi A, Deville M, Leriche E, Soldati A
Large eddy simulation of particulate flow inside a differentially heated cavity
Nuclear Engineering and Design. 2014; 267: 154-163. https://doi.org/10.1016/j.nucengdes.2013.12.035
DORA PSI
Caruso S, Jatuff F
Design, development and utilisation of a tomography station for γ-ray emission and transmission analyses of light water reactor spent fuel rods
Progress in Nuclear Energy. 2014; 72: 49-54. https://doi.org/10.1016/j.pnucene.2013.09.007
DORA PSI
Cortesi M, Dangendorf V, Zboray R, Prasser H-M
A novel fast-neutron detector concept for energy-selective imaging and imaging spectroscopy
Review of Scientific Instruments. 2014; 85(7): 073305 (8 pp.). https://doi.org/10.1063/1.4890392
DORA PSI
Cozzo C, Orlov A, Borca C, Degueldre C
X-ray absorption in plutonium uranium mixed oxide fuel: thorium characterization
Progress in Nuclear Energy. 2014; 72: 91-95. https://doi.org/10.1016/j.pnucene.2013.09.009
DORA PSI
Cripps RC, Güntay S, Jäckel B
The predicted effects of selected Phebus FPT1 sump constituents on iodine volatility
Nuclear Engineering and Design. 2014; 272: 99-108. https://doi.org/10.1016/j.nucengdes.2014.02.019
DORA PSI
Dokhane A, Ferroukhi H, Pautz A
On out-of-phase higher mode oscillations with rotation and oscillation of symmetry line using an advanced integral stability methodology
Annals of Nuclear Energy. 2014; 67: 21-30. https://doi.org/10.1016/j.anucene.2013.11.006
DORA PSI
Fernandez-Moguel L, Bals C, Beuzet E, Bratfisch C, Coindreau O, Hózer Z, et al.
SARNET2 benchmark on air ingress experiments QUENCH-10, -16
Annals of Nuclear Energy. 2014; 74: 12-23. https://doi.org/10.1016/j.anucene.2014.05.013
DORA PSI
Ferroukhi H, Leray O, Hursin M, Vasiliev A, Perret G, Pautz A
Study of nuclear decay data contribution to uncertainties in heat load estimations for spent fuel pools
Nuclear Data Sheets. 2014; 118: 498-501. https://doi.org/10.1016/j.nds.2014.04.117
DORA PSI
Fleurot J, Lindholm I, Kononen N, Ederli S, Jaeckel B, Kaliatka A, et al.
Synthesis of spent fuel pool accident assessments using severe accident codes
Annals of Nuclear Energy. 2014; 74: 58-71. https://doi.org/10.1016/j.anucene.2014.07.011
DORA PSI
Geža V, Milenković RŽ, Kapulla R, Dementjevs S, Jakovičs A, Wohlmuther M
Computational and experimental studies of the flow field near the beam entrance window of a liquid metal target
Nuclear Engineering and Design. 2014; 275: 96-106. https://doi.org/10.1016/j.nucengdes.2014.04.022
DORA PSI
Grasso G, Petrovich C, Mattioli D, Artioli C, Sciora P, Gugiu D, et al.
The core design of ALFRED, a demonstrator for the European lead-cooled reactors
Nuclear Engineering and Design. 2014; 278: 287-301. https://doi.org/10.1016/j.nucengdes.2014.07.032
DORA PSI
Hursin M, Collins B, Xu Y, Downar T
The development and implementation of a one-dimensional S_n method in the 2D-1D integral transport solution
Nuclear Science and Engineering. 2014; 176(2): 186-200. https://doi.org/10.13182/NSE12-4
DORA PSI
Ihalainen M, Lind T, Arffman A, Torvela T, Jokiniemi J
Break-Up and bounce of TiO₂ agglomerates by impaction
Aerosol Science and Technology. 2014; 48(1): 31-41. https://doi.org/10.1080/02786826.2013.852155
DORA PSI
Ihalainen M, Lind T, Ruusunen J, Tiitta P, Lähde A, Torvela T, et al.
Experimental study on bounce of submicron agglomerates upon inertial impaction
Powder Technology. 2014; 268: 203-209. https://doi.org/10.1016/j.powtec.2014.08.029
DORA PSI
Kapulla R, Mignot G, Paranjape S, Ryan L, Paladino D
Large scale gas stratification erosion by a vertical helium-air jet
Science and Technology of Nuclear Installations. 2014; 2014: 197267 (16 pp.). https://doi.org/10.1155/2014/197267
DORA PSI
Klein-Heßling W, Sonnenkalb M, Jacquemain D, Clément B, Raimond E, Dimmelmeier H, et al.
Conclusions on severe accident research priorities
Annals of Nuclear Energy. 2014; 74: 4-11. https://doi.org/10.1016/j.anucene.2014.07.015
DORA PSI
Křepel J, Hombourger B, Fiorina C, Mikityuk K, Rohde U, Kliem S, et al.
Fuel cycle advantages and dynamics features of liquid fueled MSR
Annals of Nuclear Energy. 2014; 64: 380-397. https://doi.org/10.1016/j.anucene.2013.08.007
DORA PSI
Lazaro A, Schikorr M, Mikityuk K, Ammirabile L, Bandini G, Darmet G, et al.
Code assessment and modelling for design basis accident analysis of the European sodium fast reactor design. Part II: optimised core and representative transients analysis
Nuclear Engineering and Design. 2014; 277: 265-276. https://doi.org/10.1016/j.nucengdes.2014.02.029
DORA PSI
Lindley BA, Fiorina C, Franceschini F, Lahoda EJ, Parks GT
Thorium breeder and burner fuel cycles in reduced-moderation LWRs compared to fast reactors
Progress in Nuclear Energy. 2014; 77: 107-123. https://doi.org/10.1016/j.pnucene.2014.06.010
DORA PSI
Lázaro A, Ammirabile L, Bandini G, Darmet G, Massara S, Dufour P, et al.
Code assessment and modelling for design basis accident analysis of the European sodium fast reactor design. Part I: system description, modelling and benchmarking
Nuclear Engineering and Design. 2014; 266: 1-16. https://doi.org/10.1016/j.nucengdes.2013.10.019
DORA PSI
Lüley J, Vrban B, Čerba Š, Haščík J, Nečas V, Pelloni S
Sensitivity and uncertainty analysis of the GFR MOX fuel subassembly
Nuclear Data Sheets. 2014; 118: 545-547. https://doi.org/10.1016/j.nds.2014.04.130
DORA PSI
Martin G, Garcia P, Sabathier C, Devynck F, Krack M, Maillard S
A thermal modelling of displacement cascades in uranium dioxide
Nuclear Instruments and Methods in Physics Research, Section B: Beam Interactions with Materials and Atoms. 2014; 327: 108-112. https://doi.org/10.1016/j.nimb.2013.09.043
DORA PSI
Mukin RV
Modeling of bubble coalescence and break-up in turbulent bubbly flow
International Journal of Multiphase Flow. 2014; 62: 52-66. https://doi.org/10.1016/j.ijmultiphaseflow.2014.02.008
DORA PSI
Ngayam-Happy R, Krack M
Investigation of the influence of off-stoichiometry on the radiation damage evolution in uranium dioxide
Progress in Nuclear Energy. 2014; 72: 38-43. https://doi.org/10.1016/j.pnucene.2013.09.015
DORA PSI
Papini D, Adamsson C, Andreani M, Prasser H-M
Assessment of GOTHIC and TRACE codes against selected PANDA experiments on a Passive Containment Condenser
Nuclear Engineering and Design. 2014; 278: 542-557. https://doi.org/10.1016/j.nucengdes.2014.08.007
DORA PSI
Parisi C, Negrenti E, Pecchia M
B&W spectral shift control reactor lattice experiments: evaluation of core I and core VIII
Nuclear Science and Engineering. 2014; 178(4): 524-538. https://doi.org/10.13182/NSE14-40
DORA PSI
Pelloni S
Application of an iterative methodology for cross-section and variance/covariance data adjustment to the analysis of fast spectrum systems accounting for non-linearity
Annals of Nuclear Energy. 2014; 72: 373-390. https://doi.org/10.1016/j.anucene.2014.06.002
DORA PSI
Ruusunen J, Ihalainen M, Koponen T, Torvela T, Tenho M, Salonen J, et al.
Controlled oxidation of iron nanoparticles in chemical vapour synthesis
Journal of Nanoparticle Research. 2014; 16(2): 2270 (11 pp.). https://doi.org/10.1007/s11051-014-2270-0
DORA PSI
Salvatores M, Palmiotti G, Aliberti G, Archier P, De Saint Jean C, Dupont E, et al.
Methods and issues for the combined use of integral experiments and covariance data: results of a NEA international collaborative study
Nuclear Data Sheets. 2014; 118: 38-71. https://doi.org/10.1016/j.nds.2014.04.005
DORA PSI
Toggweiler M, Adelmann A, Arbenz P, Yang J
A novel adaptive time stepping variant of the Boris-Buneman integrator for the simulation of particle accelerators with space charge
Journal of Computational Physics. 2014; 273: 255-267. https://doi.org/10.1016/j.jcp.2014.05.008
DORA PSI
Vasiliev A, Ferroukhi H, Zhu T, Pautz A
Nuclear data library effects on fast to thermal flux shapes around PWR control rod tips
Nuclear Data Sheets. 2014; 118: 575-578. https://doi.org/10.1016/j.nds.2014.04.139
DORA PSI
Zboray R, Adams R, Cortesi M, Prasser H-M
Development of a fast neutron imaging system for investigating two-phase flows in nuclear thermal-hydraulic phenomena: a status report
Nuclear Engineering and Design. 2014; 273: 10-23. https://doi.org/10.1016/j.nucengdes.2014.01.027
DORA PSI
Zboray R, Mor I, Dangendorf V, Stark M, Tittelmeier K, Cortesi M, et al.
High-frame rate imaging of two-phase flow in a thin rectangular channel using fast neutrons
Applied Radiation and Isotopes. 2014; 90: 122-131. https://doi.org/10.1016/j.apradiso.2014.03.023
DORA PSI
Zhu T, Vasiliev A, Ferroukhi H, Pautz A
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
Nuclear Data Sheets. 2014; 118: 453-455. https://doi.org/10.1016/j.nds.2014.04.104
DORA PSI
Zhu T, Rochman D, Vasiliev A, Ferroukhi H, Wieselquist W, Pautz A
Comparison of two approaches for nuclear data uncertainty propagation in MCNPX for selected fast spectrum critical benchmarks
Nuclear Data Sheets. 2014; 118: 388-391. https://doi.org/10.1016/j.nds.2014.04.088
DORA PSI
Birchley J, Güntay S
Significance of Phébus-FP results for plant safety in Switzerland
Annals of Nuclear Energy. 2013; 61: 206-214. https://doi.org/10.1016/j.anucene.2013.02.032
DORA PSI
Bortot S, Cammi A, Lorenzi S, Ponciroli R, Della Bona A, Juarez NB
Stability analyses for the European LFR demonstrator
Nuclear Engineering and Design. 2013; 265: 1238-1245. https://doi.org/10.1016/j.nucengdes.2013.09.034
DORA PSI
Bosshard C, Dehbi A, Deville M, Leriche E, Puragliesi R, Soldati A
Large eddy simulation of the differentially heated cubic cavity flow by the spectral element method
Computers and Fluids. 2013; 86: 210-227. https://doi.org/10.1016/j.compfluid.2013.07.007
DORA PSI
Chawla R, Rätz D, Jordan KA, Perret G
Analysis of pin removal experiments conducted in a supercritical light water reactor-like test lattice
Nuclear Technology. 2013; 183(3): 321-330. https://doi.org/10.13182/NT13-A19421
DORA PSI
Cortesi M, Zboray R, Kaestner A, Prasser H-M
Development of a cold-neutron imaging detector based on thick gaseous electron multiplier
Review of Scientific Instruments. 2013; 84(2): 023305 (7 pp.). https://doi.org/10.1063/1.4793225
DORA PSI
Cortesi M, Zboray R, Adams R, Dangendorf V, Meshkian M, Prasser H-M
Development of large-area THGEM detectors for investigation of thermal-hydraulic phenomena using neutron imaging
Journal of Instrumentation. 2013; 8(10): C10009 (11 pp.). https://doi.org/10.1088/1748-0221/8/10/C10009
DORA PSI
Cortesi M, Zboray R, Adams R, Dangendorf V, Breskin A, Mayer S, et al.
First studies of electron transport along small gas gaps of novel foil radiation converters for fast-neutron detectors
Journal of Instrumentation. 2013; 8(1): P01016 (19 pp.). https://doi.org/10.1088/1748-0221/8/01/P01016
DORA PSI
Dehbi A, Badreddine H
CFD prediction of mixing in a steam generator mock-up: comparison between full geometry and porous medium approaches
Annals of Nuclear Energy. 2013; 58: 178-187. https://doi.org/10.1016/j.anucene.2013.03.019
DORA PSI
Dehbi A
On the adequacy of wall functions to predict condensation rates from steam-noncondensable gas mixtures
Nuclear Engineering and Design. 2013; 265: 25-34. https://doi.org/10.1016/j.nucengdes.2013.07.014
DORA PSI
Dehbi A, Janasz F, Bell B
Prediction of steam condensation in the presence of noncondensable gases using a CFD-based approach
Nuclear Engineering and Design. 2013; 258: 199-210. https://doi.org/10.1016/j.nucengdes.2013.02.002
DORA PSI
Dokhane A, Canepa S, Ferroukhi H
Transition to CASMO-5M and SIMULATE-3K for stability analyses of the Swiss boiling water reactors
Nuclear Technology. 2013; 183(3): 341-353. https://doi.org/10.13182/NT13-A19423
DORA PSI
Fernandez-Moguel L, Birchley J
Analysis of QUENCH-10 and -16 air ingress experiments with SCDAPSim3.5
Annals of Nuclear Energy. 2013; 53: 202-212. https://doi.org/10.1016/j.anucene.2012.08.030
DORA PSI
Fiorina C, Krepel J, Cammi A, Franceschini F, Mikityuk K, Ricotti ME
Analysis of thorium and uranium fuel cycles in an iso-breeder lead fast reactor using extended-EQL3D procedure
Annals of Nuclear Energy. 2013; 53: 492-506. https://doi.org/10.1016/j.anucene.2012.09.004
DORA PSI
Fiorina C, Aufiero M, Cammi A, Franceschini F, Krepel J, Luzzi L, et al.
Investigation of the MSFR core physics and fuel cycle characteristics
Progress in Nuclear Energy. 2013; 68: 153-168. https://doi.org/10.1016/j.pnucene.2013.06.006
DORA PSI
Freixa J, Kim T-W, Manera A
Post-test thermal-hydraulic analysis of two intermediate LOCA tests at the ROSA facility including uncertainty evaluation
Nuclear Engineering and Design. 2013; 264: 153-160. https://doi.org/10.1016/j.nucengdes.2013.02.023
DORA PSI
Giust FD, Grimm P, Chawla R
Experimental validation of 3-D reconstructed pin power distributions in full-scale BWR fuel assemblies with partial-length rods
Nuclear Science and Engineering. 2013; 175(3): 292-307. https://doi.org/10.13182/NSE12-69
DORA PSI
Hursin M, Downar TJ, Montgomery R
Impact of improved neutronic methodology on the cladding response during a PWR reactivity initiated accident
Nuclear Engineering and Design. 2013; 262: 180-188. https://doi.org/10.1016/j.nucengdes.2013.04.023
DORA PSI
Khvostov G, Lyon W, Zimmermann MA
Application of the FALCON code to PCI induced cladding failure and the effects of missing pellet surface
Annals of Nuclear Energy. 2013; 62: 398-412. https://doi.org/10.1016/j.anucene.2013.07.002
DORA PSI
Kröhnert H, Perret G, Murphy MF, Chawla R
Gamma-ray spectrometric measurements of fission rate ratios between fresh and burnt fuel following irradiation in a zero-power reactor
Nuclear Instruments and Methods in Physics Research, Section A: Accelerators, Spectrometers, Detectors and Associated Equipment. 2013; 698: 72-80. https://doi.org/10.1016/j.nima.2012.09.008
DORA PSI
Ngayam-Happy R, Becquart CS, Domain C
First principle-based AKMC modelling of the formation and medium-term evolution of point defect and solute-rich clusters in a neutron irradiated complex Fe-CuMnNiSiP alloy representative of reactor pressure vessel steels
Journal of Nuclear Materials. 2013; 440(1-3): 143-152. https://doi.org/10.1016/j.jnucmat.2013.04.081
DORA PSI
Rabone J, Krack M
A procedure for bypassing metastable states in local basis set DFT+U calculations and its application to uranium dioxide surfaces
Computational Materials Science. 2013; 71: 157-164. https://doi.org/10.1016/j.commatsci.2013.01.023
DORA PSI
Rycroft CH, Dehbi A, Lind T, Güntay S
Granular flow in pebble-bed nuclear reactors: scaling, dust generation, and stress
Nuclear Engineering and Design. 2013; 265: 69-84. https://doi.org/10.1016/j.nucengdes.2013.07.010
DORA PSI
Sun K, Krepel J, Mikityuk K, Chawla R
A neutronics study for improving the safety and performance parameters of a 3600 MWth Sodium-cooled Fast Reactor
Annals of Nuclear Energy. 2013; 53: 464-475. https://doi.org/10.1016/j.anucene.2012.10.004
DORA PSI
Sun K, Chenu A, Krepel J, Mikityuk K, Chawla R
Coupled 3-D neutronics/thermal-hydraulics optimization study for improving the response of a 3600 MW(thermal) SFR core to an unprotected loss-of-flow accident
Nuclear Technology. 2013; 183(3): 484-503. https://doi.org/10.13182/NT13-A19436
DORA PSI
Tenchine D, Pialla D, Fanning TH, Thomas JW, Chellapandi P, Shvetsov Y, et al.
International benchmark on the natural convection test in Phenix reactor
Nuclear Engineering and Design. 2013; 258: 189-198. https://doi.org/10.1016/j.nucengdes.2013.02.010
DORA PSI
Wieselquist W, Zhu T, Vasiliev A, Ferroukhi H
PSI methodologies for nuclear data uncertainty propagation with CASMO-5M and MCNPX: results for OECD/NEA UAM benchmark phase I
Science and Technology of Nuclear Installations. 2013; 2013: 549793 (15 pp.). https://doi.org/10.1155/2013/549793
DORA PSI
Yang JJ, Adelmann A, Barletta W, Calabretta L, Calanna A, Campo D, et al.
Beam dynamics simulation for the high intensity DAEδALUS cyclotrons
Nuclear Instruments and Methods in Physics Research, Section A: Accelerators, Spectrometers, Detectors and Associated Equipment. 2013; 704: 84-91. https://doi.org/10.1016/j.nima.2012.12.050
DORA PSI
Zboray R, Prasser H-M
Measuring liquid film thickness in annular two-phase flows by cold neutron imaging
Experiments in Fluids. 2013; 54(9): 1596 (15 pp.). https://doi.org/10.1007/s00348-013-1596-1
DORA PSI
Zboray R, Prasser H-M
Neutron imaging of annular flows in a tight lattice fuel bundle model
Nuclear Engineering and Design. 2013; 262: 589-599. https://doi.org/10.1016/j.nucengdes.2013.06.005
DORA PSI
Zboray R, Prasser H-M
Optimizing the performance of cold-neutron tomography for investigating annular flows and functional spacers in fuel rod bundles
Nuclear Engineering and Design. 2013; 260: 188-203. https://doi.org/10.1016/j.nucengdes.2013.03.026
DORA PSI
Ammar Y, Dehbi A, Reeks MW
Break-up of aerosol agglomerates in highly turbulent gas flow
Flow, Turbulence and Combustion. 2012; 89(3): 465-489. https://doi.org/10.1007/s10494-012-9398-8
DORA PSI
Andreani M, Bittermann D, Marsault P, Antoni O, Keresztúri A, Schlagenhaufer M, et al.
Evaluation of a preliminary safety concept for the HPLWR
Progress in Nuclear Energy. 2012; 55: 68-77. https://doi.org/10.1016/j.pnucene.2011.11.004
DORA PSI
Aounallah Y
Simulation of HALDEN IFA-650 loss-of-coolant accidents tests with TRACE
Kerntechnik. 2012; 77(5): 316-323. https://doi.org/10.3139/124.110214
DORA PSI
Arazi L, Natal da Luz H, Freytag D, Pitt M, Azevedo CDR, Rubin A, et al.
THGEM-based detectors for sampling elements in DHCAL: laboratory and beam evaluation
Journal of Instrumentation. 2012; 7(5): C05011 (15 pp.). https://doi.org/10.1088/1748-0221/7/05/C05011
DORA PSI
Birchley J, Fernandez-Moguel L
Simulation of air oxidation during a reactor accident sequence: part 1 - phenomenology and model development
Annals of Nuclear Energy. 2012; 40(1): 163-170. https://doi.org/10.1016/j.anucene.2011.10.019
DORA PSI
Bottomley D, Stuckert J, Hofmann P, Tocheny L, Hugon M, Journeau C, et al.
Severe accident research in the core degradation area: an example of effective international cooperation between the European Union (EU) and the Commonwealth of Independent States (CIS) by the International Science and Technology Center
Nuclear Engineering and Design. 2012; 252: 226-241. https://doi.org/10.1016/j.nucengdes.2012.07.006
DORA PSI
Breskin A, Israelashvili I, Cortesi M, Arazi L, Shchemelinin S, Chechik R, et al.
A novel liquid-xenon detector concept for combined fast-neutrons and gamma imaging and spectroscopy
Journal of Instrumentation. 2012; 7(6): C06008 (14 pp.). https://doi.org/10.1088/1748-0221/7/06/C06008
DORA PSI
Chenu A, Adams R, Mikityuk K, Chawla R
Analysis of selected Phenix EOL tests with the FAST code system - part I: control-rod-shift experiments
Annals of Nuclear Energy. 2012; 49: 182-190. https://doi.org/10.1016/j.anucene.2012.05.036
DORA PSI
Chenu A, Mikityuk K, Chawla R
Analysis of selected Phenix EOL tests with the FAST code system - part II: unprotected phase of the Natural Convection Test
Annals of Nuclear Energy. 2012; 49: 191-199. https://doi.org/10.1016/j.anucene.2012.05.035
DORA PSI
Cortesi M, Zboray R, Adams R, Dangendorf V, Prasser H-M
Concept of a novel fast neutron imaging detector based on THGEM for fan-beam tomography applications
Journal of Instrumentation. 2012; 7(2): C02056 (11 pp.). https://doi.org/10.1088/1748-0221/7/02/C02056
DORA PSI
Devynck F, Iannuzzi M, Krack M
Frenkel pair recombinations in UO₂: importance of explicit description of polarizability in core-shell molecular dynamics simulations
Physical Review B. 2012; 85(18): 184103 (12 pp.). https://doi.org/10.1103/PhysRevB.85.184103
DORA PSI
Dietler R, Hursin M, Perret G, Jordan K, Chawla R
A novel design approach for a neutron measurement station for burnt fuel
Nuclear Instruments and Methods in Physics Research, Section A: Accelerators, Spectrometers, Detectors and Associated Equipment. 2012; 693: 59-66. https://doi.org/10.1016/j.nima.2012.07.009
DORA PSI
Epiney A, Alpy N, Mikityuk K, Chawla R
A standalone decay heat removal device for the Gas-cooled Fast Reactor for intermediate to atmospheric pressure conditions
Nuclear Engineering and Design. 2012; 242: 267-284. https://doi.org/10.1016/j.nucengdes.2011.10.011
DORA PSI
Fernandez-Moguel L, Birchley J
Simulation of air oxidation during a reactor accident sequence: part 2 - analysis of PARAMETER-SF4 air ingress experiment using RELAP5/SCDAPSIM
Annals of Nuclear Energy. 2012; 40(1): 141-152. https://doi.org/10.1016/j.anucene.2011.10.018
DORA PSI
Freixa J, Manera A
Remarks on consistent development of plant nodalizations: an example of application to the ROSA integral test facility
Science and Technology of Nuclear Installations. 2012; 2012: 158617 (17 pp.). https://doi.org/10.1155/2012/158617
DORA PSI
Freixa J, Kim T-W, Manera A
Thermal-hydraulic analysis of an intermediate LOCA test at the ROSA facility including uncertainty evaluation
Nuclear Engineering and Design. 2012; 249: 97-103. https://doi.org/10.1016/j.nucengdes.2011.08.061
DORA PSI
Girault N, Bosland L, Dickinson S, Funke F, Güntay S, Herranz LE, et al.
LWR severe accident simulation: iodine behaviour in FPT2 experiment and advances on containment iodine chemistry
Nuclear Engineering and Design. 2012; 243: 371-392. https://doi.org/10.1016/j.nucengdes.2011.11.011
DORA PSI
Ihalainen M, Lind T, Torvela T, Lehtinen KEJ, Jokiniemi J
A method to study agglomerate breakup and bounce during impaction
Aerosol Science and Technology. 2012; 46(9): 990-1001. https://doi.org/10.1080/02786826.2012.685663
DORA PSI
Kapulla R, Mignot G, Paladino D
Large-scale containment cooler performance experiments under accident conditions
Science and Technology of Nuclear Installations. 2012; 2012: 943197 (20 pp.). https://doi.org/10.1155/2012/943197
DORA PSI
Kim T, Petrov V, Manera A, Lo S
Analysis of void fraction distribution and departure from nucleate boiling in single subchannel and bundle geometries using subchannel, system, and computational fluid dynamics codes
Science and Technology of Nuclear Installations. 2012; 2012: 746467 (20 pp.). https://doi.org/10.1155/2012/746467
DORA PSI
Kim TW, Dang VN, Zimmermann MA, Manera A
Quantitative evaluation of change in core damage frequency by postulated power uprate: medium-break loss-of-coolant-accidents
Annals of Nuclear Energy. 2012; 47: 69-80. https://doi.org/10.1016/j.anucene.2012.04.021
DORA PSI
Kozmenkov Y, Rohde U, Manera A
Validation of the RELAP5 code for the modeling of flashing-induced instabilities under natural-circulation conditions using experimental data from the CIRCUS test facility
Nuclear Engineering and Design. 2012; 243: 168-175. https://doi.org/10.1016/j.nucengdes.2011.10.053
DORA PSI
Krepel J, Pelloni S, Mikityuk K
Comparison of open and closed U-Pu equilibrium fuel cycles for Generation-IV fast reactors with the EQL3D procedure
Nuclear Engineering and Design. 2012; 250: 392-402. https://doi.org/10.1016/j.nucengdes.2012.06.004
DORA PSI
Marinoni A, Girardin G, Mikityuk K
Analysis of the BN-600 fast-spectrum core mock-up at BFS-2 zero-power facility using MCNPX
Annals of Nuclear Energy. 2012; 44: 26-33. https://doi.org/10.1016/j.anucene.2012.01.011
DORA PSI
Paladino D, Dreier J
PANDA: a multipurpose integral test facility for LWR safety investigations
Science and Technology of Nuclear Installations. 2012; 2012: 239319 (9 pp.). https://doi.org/10.1155/2012/239319
DORA PSI
Paladino D, Dreier J
Passive Containment Cooling System (PCCS) response with Drywell Gas Recirculation System (DGRS) activated during a severe accident scenario with release of non-condensable gas
Nuclear Engineering and Design. 2012; 247: 212-220. https://doi.org/10.1016/j.nucengdes.2012.03.006
DORA PSI
Perret G, Jordan KA
On the combination of delayed neutron and delayed gamma measurement techniques for nuclear fuel and its application to nuclear data uncertainty reduction
IEEE Transactions on Nuclear Science. 2012; 59(6): 3166-3172. https://doi.org/10.1109/TNS.2012.2215339
DORA PSI
Rätz D, Jordan KA, Bayard A-SP, Perret G, Chawla R
Experimental investigation of moderator density variation effects in an SCWR-like fuel lattice
Nuclear Engineering and Design. 2012; 247: 236-247. https://doi.org/10.1016/j.nucengdes.2012.02.011
DORA PSI
Sharabi M, Freixa J
Analysis of the ISP-50 Direct Vessel Injection SBLOCA in the ATLAS facility with the RELAP5/MOD3.3 code
Nuclear Engineering and Technology. 2012; 44(7): 709-718. https://doi.org/10.5516/NET.02.2012.712
DORA PSI
Yun Y, Legut D, Oppeneer PM
Phonon spectrum, thermal expansion and heat capacity of UO₂ from first-principles
Journal of Nuclear Materials. 2012; 426(1-3): 109-114. https://doi.org/10.1016/j.jnucmat.2012.03.017
DORA PSI
Adamsson C, Le Corre J-M
Modeling and validation of a mechanistic tool (MEFISTO) for the prediction of critical power in BWR fuel assemblies
Nuclear Engineering and Design. 2011; 241(8): 2843-2858. https://doi.org/10.1016/j.nucengdes.2011.01.033
DORA PSI
Barten W, Jasiulevicius A, Zerkak O, Macian-Juan R
Analysis of the umsichtwater hammer benchmark experiment 329 using trace and RELAP5
Multiphase Science and Technology. 2011; 23(1): 1-27. https://doi.org/10.1615/MultScienTechn.v23.i1.10
DORA PSI
Bertolotto D, Manera A, Macián-Juan R, Chawla R
Improvement of the one-dimensional dissolved-solute convection equation using the QUICKEST-ULTIMATE algorithm
Nuclear Engineering and Design. 2011; 241(1): 245-256. https://doi.org/10.1016/j.nucengdes.2010.10.021
DORA PSI
Caravati S, Colleoni D, Mazzarello R, Kühne TD, Krack M, Bernasconi M, et al.
First-principles study of nitrogen doping in cubic and amorphous Ge₂Sb₂Te₅
Journal of Physics: Condensed Matter. 2011; 23(26): 265801 (13 pp.). https://doi.org/10.1088/0953-8984/23/26/265801
DORA PSI
Chauliac C, Aragonés J-M, Bestion D, Cacuci DG, Crouzet N, Weiss F-P, et al.
NURESIM - A European simulation platform for nuclear reactor safety: Multi-scale and multi-physics calculations, sensitivity and uncertainty analysis
Nuclear Engineering and Design. 2011; 241(9): 3416-3426. https://doi.org/10.1016/j.nucengdes.2010.09.040
DORA PSI
Chenu A, Mikityuk K, Chawla R
Pressure drop modeling and comparisons with experiments for single- and two-phase sodium flow
Nuclear Engineering and Design. 2011; 241(9): 3898-3909. https://doi.org/10.1016/j.nucengdes.2011.07.009
DORA PSI
Chylarecka D, Kim TK, Tarafder K, Müller K, Gödel K, Czekaj I, et al.
Indirect magnetic coupling of manganese porphyrin to a ferromagnetic cobalt substrate
Journal of Physical Chemistry C. 2011; 115(4): 1295-1301. https://doi.org/10.1021/jp106822s
DORA PSI
Freixa J, Manera A
Verification of a TRACE EPR™ model on the basis of a scaling calculation of an SBLOCA ROSA test
Nuclear Engineering and Design. 2011; 241(3): 888-896. https://doi.org/10.1016/j.nucengdes.2010.12.016
DORA PSI
Giust FD, Grimm P, Chawla R
Experimental comparisons of 3D reconstructed pin-power distributions in full-scale BWR fuel assemblies
Journal of Engineering for Gas Turbines and Power. 2011; 133(5): 52909 (13 pp.). https://doi.org/10.1115/1.4002823
DORA PSI
Herranz LE, Vallejo I, Khvostov G, Sercombe J, Zhou G
Assessment of fuel rod performance codes under ramp scenarios investigated within the SCIP project
Nuclear Engineering and Design. 2011; 241(3): 815 (11 pp.)-825. https://doi.org/10.1016/j.nucengdes.2011.01.007
DORA PSI
Jordan KA, Perret G
A delayed neutron technique for measuring induced fission rates in fresh and burnt LWR fuel
Nuclear Instruments and Methods in Physics Research, Section A: Accelerators, Spectrometers, Detectors and Associated Equipment. 2011; 634(1): 91-100. https://doi.org/10.1016/j.nima.2011.01.064
DORA PSI
Khvostov G, Mikityuk K, Zimmermann MA
A model for fission gas release and gaseous swelling of the uranium dioxide fuel coupled with the FALCON code
Nuclear Engineering and Design. 2011; 241(8): 2983-3007. https://doi.org/10.1016/j.nucengdes.2011.06.020
DORA PSI
Khvostov G, Wiesenack W, Zimmermann MA, Ledergerber G
Some insights into the role of axial gas flow in fuel rod behaviour during the LOCA based on Halden tests and calculations with the FALCON-PSI code
Nuclear Engineering and Design. 2011; 241(5): 1500-1507. https://doi.org/10.1016/j.nucengdes.2011.03.003
DORA PSI
Kolbe E, Vasiliev A, Ferroukhi H
Assessment of the JEFF-3.1.1 neutron data library for CSE of LWR fuel storage pools
Journal of the Korean Physical Society. 2011; 59(23): 1174-1178. https://doi.org/10.3938/jkps.59.1174
DORA PSI
Mikityuk K, Shestopalov A
FRED fuel behaviour code: Main models and analysis of Halden IFA-503.2 tests
Nuclear engineering and design. 2011; 241(7): 2455-2461. https://doi.org/10.1016/j.nucengdes.2011.04.033
DORA PSI
Modin A, Yun Y, Suzuki M-T, Vegelius J, Werme L, Nordgren J, et al.
Indication of single-crystal PuO₂ oxidation from O 1s x-ray absorption spectra
Physical Review B. 2011; 83(7): 075113 (7 pp.). https://doi.org/10.1103/PhysRevB.83.075113
DORA PSI
Nikitin K, Manera A
Analysis of an ADS spurious opening event at a BWR/6 by means of the TRACE code
Nuclear Engineering and Design. 2011; 241(6): 2240-2247. https://doi.org/10.1016/j.nucengdes.2011.03.021
DORA PSI
Pelloni S, Mikityuk K
A new cross-section generation model in the FAST code system and its application to gas- and sodium-cooled Generation IV fast reactors
Annals of Nuclear Energy. 2011; 38(1): 1-13. https://doi.org/10.1016/j.anucene.2010.08.009
DORA PSI
Perez M, Reventos F, Batet L, Guba A, Tóth I, Mieusset T, et al.
Uncertainty and sensitivity analysis of a LBLOCA in a PWR nuclear power plant: results of the phase V of the BEMUSE programme
Nuclear Engineering and Design. 2011; 241(10): 4206-4222. https://doi.org/10.1016/j.nucengdes.2011.08.019
DORA PSI
Petrov V, Manera A
Effect of pump-induced cold-leg swirls on the flow field in the RPV of the EPR^TM: CFD investigations and comparison with experimental results
Nuclear Engineering and Design. 2011; 241(5): 1478-1485. https://doi.org/10.1016/j.nucengdes.2011.02.027
DORA PSI
Pittarello R, Vasiliev A, Ferroukhi H, Chawla R
Refined Monte Carlo analysis of the H.B. Robinson-2 reactor pressure vessel dosimetry benchmark
Annals of Nuclear Energy. 2011; 38(9): 1842-1851. https://doi.org/10.1016/j.anucene.2011.05.017
DORA PSI
Rätz D, Jordan KA, Murphy MF, Perret G, Chawla R
Comparison of measured and calculated reaction rate distributions in an scwr-like test lattice
Annals of Nuclear Energy. 2011; 38(4): 794-801. https://doi.org/10.1016/j.anucene.2010.11.021
DORA PSI
Rätz D, Jordan KA, Perret G, Chawla R
Experimental validation of control rod related perturbations of moderator regions in an SCWR-like fuel lattice
Annals of Nuclear Energy. 2011; 38(11): 2319-2332. https://doi.org/10.1016/j.anucene.2011.07.007
DORA PSI
Stainsby R, Peers K, Mitchell C, Poette C, Mikityuk K, Somers J
Gas cooled fast reactor research in Europe
Nuclear Engineering and Design. 2011; 241(9): 3481-3489. https://doi.org/10.1016/j.nucengdes.2011.08.005
DORA PSI
Sun K, Krepel J, Mikityuk K, Pelloni S, Chawla R
Void reactivity decomposition for the Sodium-cooled Fast Reactor in equilibrium fuel cycle
Annals of Nuclear Energy. 2011; 38(7): 1645-1657. https://doi.org/10.1016/j.anucene.2011.02.018
DORA PSI
Vasiliev A, Kolbe E, Ferroukhi H, Pittarello R
Comparison of neutron data libraries for the analysis of the "H. B. ROBINSON-2 Pressure Vessel Benchmark" with the MCNPX code
Journal of the Korean Physical Society. 2011; 59(23): 2047-2050. https://doi.org/10.3938/jkps.59.2047
DORA PSI
Vinai P, Macian-Juan R, Chawla R
Propagation of void fraction uncertainty measures in the RETRAN-3D simulation of the Peach Bottom turbine trip
Annals of Nuclear Energy. 2011; 38(2-3): 358-370. https://doi.org/10.1016/j.anucene.2010.10.007
DORA PSI
Yun Y, Oppeneer PM
First-principles design of next-generation nuclear fuels
MRS Bulletin. 2011; 36(3): 178-184. https://doi.org/10.1557/mrs.2011.34
DORA PSI
Yun Y, Rusz J, Suzuki M-T, Oppeneer PM
First-principles investigation of higher oxides of uranium and neptunium: U₃O₈ and Np₂O₅
Physical Review B. 2011; 83(7): 075109 (10 pp.). https://doi.org/10.1103/PhysRevB.83.075109
DORA PSI
Zerkak O, Ferroukhi H
Vessel coolant mixing effects on a PWR Main Steam Line Break transient
Annals of Nuclear Energy. 2011; 38(1): 60-71. https://doi.org/10.1016/j.anucene.2010.08.016
DORA PSI
Aounallah Y
Development of a wide-range pre-CHF convective boiling correlation
Journal of Nuclear Science and Technology. 2010; 47(4): 357-366. https://doi.org/10.3327/jnst.47.357
DORA PSI
Epiney A, Mikityuk K, Chawla R
Heavy-gas injection in the Generation IV gas-cooled fast reactor for improved decay heat removal under depressurized conditions
Nuclear Engineering and Design. 2010; 240(10): 3115-3125. https://doi.org/10.1016/j.nucengdes.2010.05.030
DORA PSI
Epiney A, Mikityuk K, Chawla R
TRACE qualification via analysis of the EIR gas-loop experiments with smooth rods
Annals of Nuclear Energy. 2010; 37(6): 875-887. https://doi.org/10.1016/j.anucene.2010.01.020
DORA PSI
Freixa J, Manera A
Analysis of an RPV upper head SBLOCA at the ROSA facility using TRACE
Nuclear Engineering and Design. 2010; 240(7): 1779-1788. https://doi.org/10.1016/j.nucengdes.2010.02.007
DORA PSI
Giust F, Grimm P, Chawla R
Experimental validation of radial reconstructed pin-power distributions in full-scale BWR fuel assemblies with and without control blade
Annals of Nuclear Energy. 2010; 37(12): 1629-1639. https://doi.org/10.1016/j.anucene.2010.08.006
DORA PSI
Kolbe E, Vasiliev A, Ferroukhi H
The effect of modern thermal neutron scattering sublibraries on criticality safety evaluations of wet storage pools
Annals of Nuclear Energy. 2010; 37(3): 371-379. https://doi.org/10.1016/j.anucene.2009.12.003
DORA PSI
Kosa M, Tan J-C, Merrill CA, Krack M, Cheetham AK, Parrinello M
Probing the mechanical properties of hybrid inorganic-organic frameworks: a computational and experimental study
ChemPhysChem. 2010; 11(11): 2332-2336. https://doi.org/10.1002/cphc.201000362
DORA PSI
Krepel J, Pelloni S, Mikityuk K, Coddington P
GFR equilibrium cycle analysis with the EQL3D procedure
Nuclear Engineering and Design. 2010; 240(4): 905-917. https://doi.org/10.1016/j.nucengdes.2009.12.007
DORA PSI
Kröhnert H, Perret G, Murphy MF, Chawla R
Freshly induced short-lived gamma-ray activity as a measure of fission rates in lightly re-irradiated spent fuel
Nuclear Instruments and Methods in Physics Research, Section A: Accelerators, Spectrometers, Detectors and Associated Equipment. 2010; 624(1): 101-108. https://doi.org/10.1016/j.nima.2010.09.033
DORA PSI
Mikityuk K
Analytical model of the oxide layer build-up in complex lead-cooled systems
Nuclear Engineering and Design. 2010; 240(10): 3632-3637. https://doi.org/10.1016/j.nucengdes.2010.07.005
DORA PSI
Mikityuk K, Krepel J, Pelloni S, Chenu A, Petkevich P, Chawla R
FAST code system: review of recent developments and near-future plans
Journal of Engineering for Gas Turbines and Power. 2010; 132(10): 102915 (7 pp.). https://doi.org/10.1115/1.4000336
DORA PSI
Pérez M, Reventós F, Batet L, Pericas R, Toth I, Bazin P, et al.
Main Results of phase IV BEMUSE project: simulation of LBLOCA in an NPP
Science and Technology of Nuclear Installations. 2010; 2010: 219294 (9 pp.). https://doi.org/10.1155/2010/219294
DORA PSI
Rohde M, Marcel CP, Manera A, Van der Hagen THJJ, Shiralkar B
Investigating the ESBWR stability with experimental and numerical tools: a comparative study
Nuclear Engineering and Design. 2010; 240(2): 375-384. https://doi.org/10.1016/j.nucengdes.2008.01.016
DORA PSI
Vasiliev A, Ferroukhi H, Kolbe E
Performance of a Monte-Carlo solution for the H.B. Robinson-2 Pressure Vessel Dosimetry Benchmark
Annals of Nuclear Energy. 2010; 37(10): 1404-1410. https://doi.org/10.1016/j.anucene.2010.05.019
DORA PSI
Walker C, Manera A, Niceno B, Simiano M, Prasser HM
Steady-state RANS-simulations of the mixing in a T-junction
Nuclear Engineering and Design. 2010; 240(9): 2107-2115. https://doi.org/10.1016/j.nucengdes.2010.05.056
DORA PSI

Break-Up and Bounce of TiO2 Agglomerates by Impaction
M. Ihalainen, T.M. Lind, A. Arffman, T. Torvela, J.K. Jokiniemi
Aerosol Science and Technology 48, 31
http://dx.doi.org/10.1080/02786826.2013.852155

Conclusions on severe accident research priorities
W. Klein-Heßling, M. Sonnenkalb, D. Jacquemain, B. Clément, E. Raimond, H. Dimmelmeier, G. Azarian, G. Ducros, C. Journeau, L.E. Herranz Puebla, A. Schumm, A. Miassoedov, I. Kljenak, G. Pascal, S. Bechta, S. Güntay, M.K. Koch, I. Ivanov, A. Auvinen, I. Lindholm
Annals of Nuclear Energy 74, 4
http://dx.doi.org/10.1016/j.anucene.2014.07.015

Synthesis of spent fuel pool accident assessments using severe accident codes
J. Fleurot, I. Lindholm, N. Kononen, B.S. Jäckel, A. Kaliatka, J. Duspiva, M. Steinbrück, T. Hollands
Annals of Nuclear Energy 74, 58
http://dx.doi.org/10.1016/j.anucene.2014.07.011

Experimental study on bounce of submicron agglomerates upon inertial impaction
M. Ihalainen, T.M. Lind, J. Ruusunen, P. Tiitta, A. Lahde, T. Torvela, J. Jokiniemi
Powder Technology 268, 203
http://dx.doi.org/10.1016/j.powtec.2014.08.029

Significance of Phébus-FP results for plant safety in Switzerland
J.C. Birchley, S. Güntay
Annals of Nuclear Energy 61, 206
http://dx.doi.org/10.1016/j.anucene.2013.02.032

Granular flow in pebble-bed nuclear reactors: Scaling,dust generation, and stress
C.H. Rycroft, A. Dehbi, T.M. Lind, S. Güntay
Nuclear Engineering and Design 265, 69
http://dx.doi.org/10.1016/j.nucengdes.2013.07.010

On the adequacy of wall functions to predict condensation rates fromsteam-noncondensable gas mixtures
A. Dehbi
Nuclear Engineering and Design 265, 25
http://dx.doi.org/10.1016/j.nucengdes.2013.07.014

A Method to Study Agglomerate Breakup and Bounce During Impaction
M. Ihalainen, T.M. Lind, T. Torvela, K.E.J. Lehtinen, J.K. Jokiniemi
Aerosol Science and Technology 46, 990
http://dx.doi.org/10.1080/02786826.2012.685663

Severe accident research in the core degradation area: An example of effective international cooperation between the European Union (EU) and the Commonwealth of Independent States (CIS) by the International Science and Technology Center
D. Bottomley, J. Stuckert, P. Hofmann, L. Tocheny, M. Hugon, C. Journeau, B. Clement, S. Weber, S. Güntay, Z. Hozer, L.E. Herranz, A. Schumm, F. Oriolo, E. Altstadt, M. Krause, M. Fischer, V.B. Khabensky, S.V. Bechta, M.S. Veshchunov, A.V. Palagin, A.E. Kiselev, V.I. Nalivaev, A.V. Goryachev, V. Zhdanov, V. Baklanov
Nuclear Engineering and Design 252, 226
http://dx.doi.org/10.1016/j.nucengdes.2012.07.006

LWR severe accident simulation: Iodine behaviour in FPT2 experiment and advances on containment iodine chemistry
N. Girault, L. Bosland, S. Dickinson, F. Funke, S. Güntay, L.E. Herranz, D. Powers
Nuclear Engineering and Design 243, 371
http://dx.doi.org/10.1016/j.nucengdes.2011.11.011

Effect Of Pump-Induced Cold-Leg Swirls On The Flow Field In The Rpv Of The Epr - Cfd Investigations And Comparison With Experimental Results
V. Petrov, A. Manera
Nuclear Engineering And Design, Vol. 241, Issue 5, May 2011, Pp 1476-1485 (2011)

Verification Of A Trace Epr Model On The Basis Of A Scaling Calculation Of An Sbloca Rosa Test
J. Freixa, A. Manera
Nuclear Engineering And Design, Volume 241, Issue 3, March 2011, P 888-896 (2011)

Modeling And Validation Of A Mechanistic Tool (Mefisto) For The Prediction Of Critical Power In Bwr Fuel Assemblies
C. Adamsson, J-M. Le Corre
Nuclear Engineering And Design, Vol. 241, Issue 8, Pp 2843-2858, August 2011

First principles Investigation Of Higher Oxides Of Uranium And Neptunium: U3o8 And Np20
Y. Yun, J. Rusz, M-T. Suzuki, P.M. Oppeneer
Physical Review, B 83, 075109, Doi: 10.1103/Phyrevb.83.075109(2011)

Sustainable integration of EU research in severe accident phenomenology and management
J.P. Van Dorsselaere, T. Albiol, B. Chaumont, T.J. Haste, C. Journeau, L. Meyer, B.R. Sehgal, B. Schwinges, D. Beraha, A. Annunziato, R. Zeyen
Nuclear Engineering and Design 241, 3451
http://dx.doi.org/10.1016/j.nucengdes.2011.01.053

Experimental and calculation results of the integral reflood test QUENCH-15 with ZIRLO (TM) cladding tubes in comparison with results of previous QUENCH tests
J. Stuckert, J.C. Birchley, M. Große, B.S. Jäckel, M. Steinbrück
Nuclear Engineering and Design 241, 3224
http://dx.doi.org/10.1016/j.nucengdes.2011.05.004

Analyses of the Phebus FPT3 Experiment using the Severe Accident Codes ATHLET-CD, ICARE/CATHARE and MELCOR
G. Repetto, O. De Luze, T. Drath, M.K. Koch, T. Hollands, K. Trambauer, C. Bals, H. Austregesilo, J.C. Birchley
Nuclear Technology 176, 352

The Once-through Mode of Steam Generator Refulx Condensation in Loss-of-Coolant Accident Scenarios
Y. Liao, S. Güntay, D.J. Suckow
Nuclear Technology 175, 510

Prediction of extrathoracic aerosol deposition using RANS-Random Walk and LES approaches
A. Dehbi
Aerosol Science and Technology 45, 555
http://dx.doi.org/10.1080/02786826.2010.550962

Improvements Of The One-Dimensional Dissolved Solute Convection Equation Using The Quickest-Ultimate Algorithm
D. Bertolotto, A. Manera, R. Macian-Juan, R. Chawla
Nuclear Engineering and Design,
http://dx.doi.org/10.1016/J.Nucengdes.2010.10.021 (2010)

Performance Of A Monte-Carlo Solution To The H.B. Robinson-2 Pressure Vessel Dosimetry Benchmark
A. Vasiliev, H. Ferroukhi, E. Kolbe
Annals of Nuclear Energy 37(2010), Pp. 1404-1410, 2010

First_principles Study Of Helium Behavior In Nuclear Fuel Materials
Y. Yun, O. Eriksson, P. M. Oppeneer
Chapter 7, Nova Science Publishers, Helium: Characteristics, Compounds And Applications, Isbn:978-1-61761-213-8 (2010)

Main Results Of Phase Iv Bemuse Project. Simulation Of Lbloca In A Npp
M. PéRez, F. ReventóS, L. Batet, R. Pericas, I. Toth, P. Bazin, CréCy. De, Germain. A, Borisov. P, Glaeser. S, Skorek. H, Joucla. T, Probst. J, Ui. P, Chung. A, Oh. B, Y. D, M. Kyncl, R. Pernica, A. Manera, F. D'Auria, A. Petruzzi, Nevo. Del,
Science And Technology of Nuclear Installations (Issn 1687-6075), Vol. 2010, Id 219294 (2010)

Experimental and calculation results of the integral reflood test QUENCH-14 with M5 (R) cladding tubes
J. Stuckert, J.C. Birchley, M. Große, B.S. Jäckel, M. Steinbrück
Annals of Nuclear Energy 37, 1036
http://dx.doi.org/10.1016/j.anucene.2010.04.015

Aerosol behavior during SIC control rod failure in QUENCH-13 test
T.M. Lind, A.P. Csordas, I. Nagy, J. Stuckert
Journal of Nuclear Materials 397, 92
http://dx.doi.org/10.1016/j.nucmat.2009.12.013

Implementation of a generalized diffusion layer model for condensation into MELCOR
K. Hogan, Y. Liao, B. Beeny, K. Vierow, R.Jr. Cole, L.L. Humphries, R.O. Gauntt
Nuclear Engineering and Design 240, 3202
http://dx.doi.org/10.1016/j.nucengdes.2010.05.059

De-agglomeration mechanisms of TiO2 aerosol agglomerates in PWR steam generator tube rupture conditions
T.M. Lind, Y. Ammar, A. Dehbi, S. Güntay
Nuclear Engineering and Design 240, 2046
http://dx.doi.org/10.1016/j.nucengdes.2010.03.002

Accident management following loss-of-coolant accidents during cooldown in a Westinghouse two-loop PWR
T.J. Haste, J.C. Birchley, M. Richner
Nuclear Engineering and Design 240, 1599
http://dx.doi.org/10.1016/j.nucengdes.2010.02.006

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. Sulatsky, V.V. Gusarov, V.I. Almyashev, G. Ducros, C. Journeau, D. Bottomley, B. Clement, L.E. Herranz, S. Güntay, K. Trambauer, A. Auvinen, V.V. Bezlepkin
Nuclear Engineering and Design 240, 1229
http://dx.doi.org/10.1016/j.nucengdes.2010.01.008

Benchmark study on fuel bundle degradation in the Pebus FPT2 test using state-of-the-art severe accident analysis codes
B. Tóth, A. Bieliauskas, G. Bandini, J.C. Birchley, H. Wada, J. Hohorst, C. Jamond, K. Trambauer
Nuclear Technology 169, 81
http://epubs.ans.org/download/?a=9354

Validation against DNS statistics of the normalized Langevin model for particletransport in turbulent channel flows
A. Dehbi
Powder Technology 200, 60
http://dx.doi.org/10.1016/j.powtec.2010.02.009

Monodisperse fine aerosol generation using fluidized bed
T.M. Lind, S. Danner, S. Güntay
Powder Technology 199, 232
http://dx.doi.org/10.1016/j.powtec.2010.01.011

Recent advances in understanding ruthenium behaviour under air-ingress conditions during a PWR severe accident
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
Progress in Nuclear Energy 52, 109
http://dx.doi.org/10.1016/j.pnucene.2009.09.011

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
Progress in Nuclear Energy 52, 97
http://dx.doi.org/10.1016/j.pnucene.2009.09.012

B₄C oxidation modelling in severe accident codes: Applications to PHEBUS and QUENCH experiments
G. Repetto, O. De Luze, N. Seiler, K. Trambauer, H. Austregesilo, J.C. Birchley, S. Ederli, J.S. Lamy, B. Maliverney, T. Drath, T. Hollands
Progress in Nuclear Energy 52, 37
http://dx.doi.org/10.1016/j.pnucene.2009.09.017

High-temperature oxidation and quench behaviour of Zircaloy-4 and E110 cladding alloys
M. Steinbrück, J.C. Birchley, A.V. Boldyrev, A.V. Goryachev, M. Grosse, T.J. Haste, Z. Hózer, A.E. Kisselev, V.I. Nalivaev, V.P. Semishkin, L. Sepold, J. Stuckert, N. Vér, M.S. Veshchunov
Progress in Nuclear Energy 52, 19
http://dx.doi.org/10.1016/j.pnucene.2009.07.012

Ranking of severe accident research priorities
B. Schwinges, C. Journeau, T.J. Haste, L. Meyerd, W. Tromm, K. Trambauer
Progress in Nuclear Energy 52, 11
http://dx.doi.org/10.1016/j.pnucene.2009.09.006

SARNET: Severe accident research network of excellence
T. Albiol, J.P. Van Dorsselaere, B. Chaumont, T.J. Haste, C. Journeau, L. Meyer, B.R. Sehgal, B. Schwinges, D. Beraha, A. Annunziato, R. Zeyen
Progress in Nuclear Energy* 52, 2
http://dx.doi.org/10.1016/j.pnucene.2009.07.011

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2005 - 2009

Bertolotto D, Manera A, Frey S, Prasser H-M, Chawla R
Single-phase mixing studies by means of a directly coupled CFD/system-code tool
Annals of Nuclear Energy. 2009; 36(3): 310-316. https://doi.org/10.1016/j.anucene.2008.11.027
DORA PSI
Caravati S, Bernasconi M, Kühne TD, Krack M, Parrinello M
First-principles study of crystalline and amorphous Ge₂Sb₂Te₅ and the effects of stoichiometric defects
Journal of Physics: Condensed Matter. 2009; 21(25): 255501 (14 pp.). https://doi.org/10.1088/0953-8984/21/25/255501
DORA PSI
Caravati S, Bernasconi M, Kühne TD, Krack M, Parrinello M
Unravelling the mechanism of pressure induced amorphization of phase change materials
Physical Review Letters. 2009; 102(20): 205502 (4 pp.). https://doi.org/10.1103/PhysRevLett.102.205502
DORA PSI
Caruso S, Murphy MF, Jatuff F, Chawla R
Determination of within-rod caesium and europium isotopic distributions in high burnup fuel rods through computerised gamma-ray emission tomography
Nuclear Engineering and Design. 2009; 239(7): 1220-1228. https://doi.org/10.1016/j.nucengdes.2009.02.019
DORA PSI
Chawla R
Editorial
Annals of Nuclear Energy. 2009; 36(3): 255-257. https://doi.org/10.1016/j.anucene.2008.11.008
DORA PSI
Chenu A, Mikityuk K, Chawla R
TRACE simulation of sodium boiling in pin bundle experiments under loss-of-flow conditions
Nuclear Engineering and Design. 2009; 239(11): 2417-2429. https://doi.org/10.1016/j.nucengdes.2009.07.015
DORA PSI
Cucinotta CS, Miceli G, Raiteri P, Krack M, Kühne TD, Bernasconi M, et al.
Superionic conduction in substoichiometric LiAl alloy: an Ab Initio study
Physical Review Letters. 2009; 103(12): 125901 (4 pp.). https://doi.org/10.1103/PhysRevLett.103.125901
DORA PSI
Ferroukhi H, Zerkak O, Chawla R
Cross-section modelling effects on pressurised water reactor main steam line break analyses
Annals of Nuclear Energy. 2009; 36(8): 1184-1200. https://doi.org/10.1016/j.anucene.2009.04.006
DORA PSI
Ferroukhi H, Hollard JM, Zimmermann MA, Chawla R
Estimation of the fast neutron fluence at control rod tips using a 3-D diffusion/2-D transport multi-step calculation scheme
Annals of Nuclear Energy. 2009; 36(3): 286-291. https://doi.org/10.1016/j.anucene.2008.12.010
DORA PSI
Ferroukhi H, Zimmermann MA
Study of the PWR REA pulse width for realistic UO2 and MOX core designs using 3D kinetics methods
Annals of Nuclear Energy. 2009; 36(8): 1170-1183. https://doi.org/10.1016/j.anucene.2009.04.007
DORA PSI
Jatuff F, Perret G, Murphy MF, Giust F, Chawla R
Void reactivity coefficient benchmark results for a 10 × 10 BWR assembly in the full 0-100% void fraction range
Annals of Nuclear Energy. 2009; 36(6): 853-858. https://doi.org/10.1016/j.anucene.2009.02.013
DORA PSI
Kato Y, Tsuzuki N, Nikitin K, Ishizuka T
Advanced microchannel heat exchanger with S-shaped fins
Journal of Nuclear Science and Technology. 2009; 46(5): 403-412. https://doi.org/10.1080/18811248.2007.9711547
DORA PSI
Krepel J, Pelloni S, Mikityuk K, Coddington P
EQL3D: ERANOS based equilibrium fuel cycle procedure for fast reactors
Annals of Nuclear Energy. 2009; 36(5): 550-561. https://doi.org/10.1016/j.anucene.2009.01.008
DORA PSI
Kühne TD, Krack M, Parrinello M
Static and dynamical properties of liquid water from first principles by a novel Car-Parrinello-like approach
Journal of Chemical Theory and Computation. 2009; 5(2): 235-241. https://doi.org/10.1021/ct800417q
DORA PSI
Liu L-M, Krack M, Michaelides A
Interfacial water: a first principles molecular dynamics study of a nanoscale water film on salt
Journal of Chemical Physics. 2009; 130(23): 234702 (12 pp.). https://doi.org/10.1063/1.3152845
DORA PSI
Manera A, Ozar B, Paranjape S, Ishii M, Prasser H-M
Comparison between wire-mesh sensors and conductive needle-probes for measurements of two-phase flow parameters
Nuclear Engineering and Design. 2009; 239(9): 1718-1724. https://doi.org/10.1016/j.nucengdes.2008.06.015
DORA PSI
Mikityuk K
Heat transfer to liquid metal: review of data and correlations for tube bundles
Nuclear Engineering and Design. 2009; 239(4): 680-687. https://doi.org/10.1016/j.nucengdes.2008.12.014
DORA PSI
Perret G, Murphy MF, Jatuff F, Sublet JC, Bouland O, Chawla R
Impact of new gadolinium cross sections on reaction rate distributions in 10×10 BWR assemblies
Nuclear Science and Engineering. 2009; 163(1): 17-25. https://doi.org/10.13182/NSE08-55
DORA PSI
Petkevich P, Mikityuk K, Coddington P, Chawla R
Development and benchmarking of a mechanical model for GFR plate-type fuel
Annals of Nuclear Energy. 2009; 36(8): 1262-1269. https://doi.org/10.1016/j.anucene.2009.01.015
DORA PSI
Plaschy M, Murphy M, Jatuff F, Lüthi A, Grimm P, Jacot-Guillarmod R, et al.
Experimental validation of reaction rate distributions for a SVEA-96+ BWR assembly with hafnium control blades
Journal of Nuclear Science and Technology. 2009; 46(9): 933-943. https://doi.org/10.3327/jnst.46.933
DORA PSI
Plaschy M, Murphy M, Jatuff F, Lüthi A, Grimm P, Jacot-Guillarmod R, et al.
Experimental validation of reaction rate distributions for a SVEA-96+ BWR assembly with hafnium control blades
Journal of Nuclear Science and Technology. 2009; 46(9): 933-943. https://doi.org/10.1080/18811248.2009.9711602
DORA PSI
Plaschy M, Murphy M, Jatuff F, Perret G, Seiler R, Chawla R
Validation of Monte Carlo predictions of LWR-PROTEUS safety parameters using an improved whole-reactor model
Annals of Nuclear Energy. 2009; 36(10): 1536-1543. https://doi.org/10.1016/j.anucene.2009.07.012
DORA PSI
Romano A, Shuffler CA, Garkisch HD, Olander DR, Todreas NE
Fuel performance analysis for PWR cores
Nuclear Engineering and Design. 2009; 239(8): 1481-1488. https://doi.org/10.1016/j.nucengdes.2008.11.022
DORA PSI
Stainsby R, Peers K, Mitchell C, Poette C, Mikityuk K, Somers J
Gas cooled fast reactor research and development in the European Union
Science and Technology of Nuclear Installations. 2009; 2009: 238624 (7 pp.). https://doi.org/10.1155/2009/238624
DORA PSI
Tsuzuki N, Kato Y, Nikitin K, Ishizuka T
Advanced microchannel heat exchanger with S-shaped fins
Journal of Nuclear Science and Technology. 2009; 46(5): 403-412. https://doi.org/10.3327/jnst.46.403
DORA PSI
Aounallah Y
A separate-effect-based new appraisal of convective boiling and its suppression
Journal of Nuclear Science and Technology. 2008; 45(2): 149-159. https://doi.org/10.3327/jnst.45.149
DORA PSI
Aounallah Y
A separate-effect-based new appraisal of convective boiling and its suppression
Journal of Nuclear Science and Technology. 2008; 45(2): 149-159. https://doi.org/10.1080/18811248.2008.9711424
DORA PSI
Barten W, Jasiulevicius A, Manera A, Macian-Juan R, Zerkak O
Analysis of the capability of system codes to model cavitation water hammers: simulation of UMSICHT water hammer experiments with TRACE and RELAP5
Nuclear Engineering and Design. 2008; 238(4): 1129-1145. https://doi.org/10.1016/j.nucengdes.2007.10.004
DORA PSI
Barten W, Manera A, Macian-Juan R
One- and two-dimensional standing pressure waves and one-dimensional travelling pulses using the US-NRC nuclear systems analysis code TRACE
Nuclear Engineering and Design. 2008; 238(10): 2568-2582. https://doi.org/10.1016/j.nucengdes.2008.05.004
DORA PSI
Blair P, Khvostov G, Romano A, Hellwig C, Chawla R
Interpretation of high-burnup fuel annealing tests
Journal of Nuclear Science and Technology. 2008; 45(7): 639-646. https://doi.org/10.1080/18811248.2008.9711463
DORA PSI
Blanchet D, Huot N, Sireta P, Serviere H, Boyard M, Antony M, et al.
Qualification of a gamma-ray heating calculation scheme for the future Jules Horowitz material testing reactor (RJH)
Annals of Nuclear Energy. 2008; 35(4): 731-745. https://doi.org/10.1016/j.anucene.2007.07.021
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
Progress in Nuclear Energy. 2008; 50(1): 37-51. https://doi.org/10.1016/j.pnucene.2007.11.090
DORA PSI
Bubelis E, Coddington P, Mikityuk K
Verification of the TRACE code against the MEGAPIE transient data
Annals of Nuclear Energy. 2008; 35(7): 1284-1295. https://doi.org/10.1016/j.anucene.2007.12.006
DORA PSI
Caruso S, Günther-Leopold I, Murphy MF, Jatuff F, Chawla R
Comparison of optimised germanium gamma spectrometry and multicollector inductively coupled plasma mass spectrometry for the determination of ¹³⁴Cs, ¹³⁷Cs and ¹⁵⁴Eu single ratios in highly burnt UO₂
Nuclear Instruments and Methods in Physics Research, Section A: Accelerators, Spectrometers, Detectors and Associated Equipment. 2008; 589(3): 425-435. https://doi.org/10.1016/j.nima.2008.03.005
DORA PSI
Caruso S, Murphy MF, Jatuff F, Chawla R
Nondestructive determination of fresh and spent nuclear fuel rod density distributions through computerised gamma-ray transmission tomography
Journal of Nuclear Science and Technology. 2008; 45(8): 828-835. https://doi.org/10.3327/jnst.45.828
DORA PSI
Chawla R, Jatuff F, Tani F
Diagnostic analysis of pin-removal reactivity worth experiments in a SVEA-96+ test lattice
Annals of Nuclear Energy. 2008; 35(3): 495-502. https://doi.org/10.1016/j.anucene.2007.06.027
DORA PSI
Cometto M, Wydler P, Chawla R
Management of actinide waste inventories in nuclear phase-out scenarios
Annals of Nuclear Energy. 2008; 35(8): 1447-1460. https://doi.org/10.1016/j.anucene.2008.01.016
DORA PSI
Girardin G, Rimpault G, Morin F, Bosq JC, Coddington P, Mikityuk K, et al.
Development and characterization of the control assembly system for the large 2400 MWth Generation IV gas-cooled fast reactor
Annals of Nuclear Energy. 2008; 35(12): 2206-2218. https://doi.org/10.1016/j.anucene.2008.09.008
DORA PSI
Kolbe E, Vasiliev A, Ferroukhi H, Zimmermann MA
Consistent evaluation of modern nuclear data libraries for criticality safety analyses of thermal compound low-enriched-uranium systems
Annals of Nuclear Energy. 2008; 35(10): 1831-1841. https://doi.org/10.1016/j.anucene.2008.04.009
DORA PSI
Kosa M, Krack M, Cheetham AK, Parrinello M
Modeling the hydrogen storage materials with exposed M²⁺ coordination sites
Journal of Physical Chemistry C. 2008; 112(42): 16171-16173. https://doi.org/10.1021/jp806394g
DORA PSI
Krepel J, Rohde U, Grundmann U, Weiss F-P
Dynamics of molten salt reactors
Nuclear Technology. 2008; 164(1): 34-44. https://doi.org/10.13182/NT08-A4006
DORA PSI
Lebrat JF, Aliberti G, D'Angelo A, Billebaud A, Brissot R, Brockmann H, et al.
Global results from deterministic and stochastic analysis of the MUSE-4 experiments on the neutronics of accelerator-driven systems
Nuclear Science and Engineering. 2008; 158(1): 49-67. https://doi.org/10.13182/NSE05-100
DORA PSI
Liu L, Krack M, Michaelides A
Density oscillations in a nanoscale water film on salt: insight from ab initio molecular dynamics
Journal of the American Chemical Society. 2008; 130(27): 8572-8573. https://doi.org/10.1021/ja8014296
DORA PSI
Mikityuk K, Coddington P, Gröschel F
Analysis of radioactivity releases in the MEGAPIE reference accident
Nuclear Engineering and Design. 2008; 238(7): 1838-1844. https://doi.org/10.1016/j.nucengdes.2007.12.004
DORA PSI
Murphy MF, Jatuff F, Perret G, Plaschy M, Bergmann U, Chawla R
Comparison of 3D reaction rate distributions measured in an Optima2 BWR assembly with MCNPX predictions
Annals of Nuclear Energy. 2008; 35(11): 2042-2050. https://doi.org/10.1016/j.anucene.2008.06.001
DORA PSI
Perret G, Plaschy M, Murphy MF, Jatuff F, Chawla R
Characterisation of radial reaction rate distributions across the 92-pin section of a SVEA-96 Optima2 assembly
Annals of Nuclear Energy. 2008; 35(3): 478-484. https://doi.org/10.1016/j.anucene.2007.06.025
DORA PSI
Vasiliev A, Ferroukhi H, Zimmermann MA, Chawla R
On the effects of oxygen cross-sections in the fast neutron fluence analysis for a reactor pressure vessel scraping test
Annals of Nuclear Energy. 2008; 35(4): 565-569. https://doi.org/10.1016/j.anucene.2007.08.018
DORA PSI
Vasiliev A, Kolbe E, Ferroukhi H, Zimmermann MA, Chawla R
On the performance of ENDF/B-VII.0 data for fast neutron fluence calculations
Annals of Nuclear Energy. 2008; 35(12): 2432-2435. https://doi.org/10.1016/j.anucene.2008.07.009
DORA PSI
Vasiliev A, Kolbe E, Zimmermann MA
Towards the development of upper subcriticality limits on the basis of benchmark criticality calculations
Annals of Nuclear Energy. 2008; 35(9): 1764-1773. https://doi.org/10.1016/j.anucene.2008.01.017
DORA PSI
Bart G, Bakker K, Hellwig C, Kihara Y, Ozawa T, Wallin H, et al.
Fuji, an initial sintering comparison test for pelletized-, sphere-pac-and vipac-fast breeder reactor mixed oxide fuel
Journal of Nuclear Science and Technology. 2007; 44(3): 329-336. https://doi.org/10.1080/18811248.2007.9711290
DORA PSI
Bergmann UC, Grimm P, Jatuff F, Murphy MF, Chawla R
Investigations of ²³⁸U captures to total fissions in a Westinghouse SVEA-96+ assembly
Nuclear Science and Engineering. 2007; 156(1): 86-95. https://doi.org/10.13182/NSE07-A2687
DORA PSI
Caruso S, Murphy M, Jatuff F, Chawla R
Validation of of ¹³⁴Cs, ¹³⁷Cs and ¹⁵⁴Eu single ratios as burnup monitors for ultra-high burnup UO₂ fuel
Annals of Nuclear Energy. 2007; 34(1-2): 28-35. https://doi.org/10.1016/j.anucene.2006.11.009
DORA PSI
Dokhane A, Hennig D, Rizwan-uddin, Chawla R
BWR stability and bifurcation analysis using reduced order models and system codes: identification of a subcritical Hopf bifurcation using RAMONA
Annals of Nuclear Energy. 2007; 34(10): 792-802. https://doi.org/10.1016/j.anucene.2007.04.003
DORA PSI
Dokhane A, Hennig D, Rizwan-uddin, Chawla R
Interpretation of in-phase and out-of-phase BWR oscillations using an extended reduced order model and semi-analytical bifurcation analysis
Annals of Nuclear Energy. 2007; 34(4): 271-287. https://doi.org/10.1016/j.anucene.2006.12.005
DORA PSI
Macian R, Zimmermann MA, Chawla R
Statistical uncertainty analysis applied to fuel depletion calculations
Journal of Nuclear Science and Technology. 2007; 44(6): 875-885. https://doi.org/10.3327/jnst.44.875
DORA PSI
Macku K, Jatuff F, Murphy M, Plaschy M, Grimm P, Joneja OP, et al.
Radial and azimuthal ²³⁵U fission and ²³⁸U capture distributions in BWR UO₂ pins: CASMO-4 and MCNP4C versus activation foil measurements
Nuclear Science and Engineering. 2007; 155(1): 96-101. https://doi.org/10.13182/NSE07-A2647
DORA PSI
Mikityuk K, Coddington P, Pelloni S, Bubelis E, Chawla R
Comparative transient analysis of critical and subcritical 80-MW Pb-Bi eutectic–cooled reactor systems
Nuclear Technology. 2007; 157(1): 18-36. https://doi.org/10.13182/NT07-A3799
DORA PSI
Milenković RŽ, Sigg B, Yadigaroglu G
Bubble clustering and trapping in large vortices. Part 1: triggered bubbly jets investigated by phase-averaging
International Journal of Multiphase Flow. 2007; 33(10): 1088-1110. https://doi.org/10.1016/j.ijmultiphaseflow.2007.05.003
DORA PSI
Petkevich P, Mikityuk K, Coddington P, Chawla R
Development and benchmarking of a 2D transient thermal model for GFR plate-type fuel
Annals of Nuclear Energy. 2007; 34(9): 707-718. https://doi.org/10.1016/j.anucene.2007.03.009
DORA PSI
Romano A, Horvath MI, Restani R
Evolution of porosity in the high-burnup fuel structure
Journal of Nuclear Materials. 2007; 361(1): 62-68. https://doi.org/10.1016/j.jnucmat.2006.09.016
DORA PSI
Stoenescu R, Schaeublin R, Gavillet D, Baluc N
Mechanical properties-microstructure correlation in neutron irradiated heat-affected zones of austenitic stainless steels
Journal of Nuclear Materials. 2007; 362(2-3): 287-292. https://doi.org/10.1016/j.jnucmat.2007.01.251
DORA PSI
Stoenescu R, Schäublin R, Gavillet D, Baluc N
Welding-induced mechanical properties in austenitic stainless steels before and after neutron irradiation
Journal of Nuclear Materials. 2007; 360(3): 255-264. https://doi.org/10.1016/j.jnucmat.2006.10.009
DORA PSI
Stoenescu R, Schäublin R, Gavillet D, Baluc N
Welding-induced microstructure in austenitic stainless steels before and after neutron irradiation
Journal of Nuclear Materials. 2007; 360(2): 186-195. https://doi.org/10.1016/j.jnucmat.2006.10.007
DORA PSI
Vasiliev A, Ferroukhi H, Zimmermann MA, Chawla R
Development of a CASMO-4/SIMULATE-3/MCNPX calculation scheme for PWR fast neutron fluence analysis and validation against RPV scraping test data
Annals of Nuclear Energy. 2007; 34(8): 615-627. https://doi.org/10.1016/j.anucene.2007.02.020
DORA PSI
Vinai P, Macian-Juan R, Chawla R
A statistical methodology for quantification of uncertainty in best estimate code physical models
Annals of Nuclear Energy. 2007; 34(8): 628-640. https://doi.org/10.1016/j.anucene.2007.03.003
DORA PSI
Zerkak O, Coddington P, Eitschberger H
Analysis of the Leibstadt power plant condensate and feedwater systems during selected operational transients
Nuclear Engineering and Design. 2007; 237(11): 1195-1208. https://doi.org/10.1016/j.nucengdes.2007.01.011
DORA PSI
Barten W, Coddington P, Ferroukhi H
RETRAN-3D analysis of the base case and the four extreme cases of the OECD/NRC Peach Bottom 2 Turbine Trip benchmark
Annals of Nuclear Energy. 2006; 33(2): 99-118. https://doi.org/10.1016/j.anucene.2005.09.011
DORA PSI
Bergmann UC, Chawla R, Jatuff F, Murphy MF
Optimised non-invasive method to determine ²³⁸U-captures-to-total-fissions in reactor fuel
Nuclear Instruments and Methods in Physics Research, Section A: Accelerators, Spectrometers, Detectors and Associated Equipment. 2006; 556(1): 331-338. https://doi.org/10.1016/j.nima.2005.08.110
DORA PSI
Blair P, Romano A, Hellwig C, Chawla R
Calculations on fission gas behaviour in the high burnup structure
Journal of Nuclear Materials. 2006; 350(3): 232-239. https://doi.org/10.1016/j.jnucmat.2006.01.006
DORA PSI
Dokhane A, Ferroukhi H, Zimmermann MA, Aguirre C
Spatial and model-order based reactor signal analysis methodology for BWR core stability evaluation
Annals of Nuclear Energy. 2006; 33(16): 1329-1338. https://doi.org/10.1016/j.anucene.2006.08.010
DORA PSI
Grimm P, Jatuff F, Murphy M, Seiler R, Williams T, Jacot-Guillarmod R, et al.
Experimental validation of channel bowing effects on pin power distributions in a Westinghouse SVEA-96+ assembly
Journal of Nuclear Science and Technology. 2006; 43(3): 223-230. https://doi.org/10.1080/18811248.2006.9711084
DORA PSI
Grimm P, Jatuff F, Murphy M, Seiler R, Williams T, Jacot-Guillarmod R, et al.
Experimental validation of channel bowing effects on pin power distributions in a Westinghouse SVEA-96+ assembly
Journal of Nuclear Science and Technology. 2006; 43(3): 223-230. https://doi.org/10.3327/jnst.43.223
DORA PSI
Jasiulevičius A, Sehgal BR
Experimental investigation of debris bed quenching with non-condensable gas release
Energetika. 2006; 3(1): 1-8.
DORA PSI
Jatuff F, Giust F, Krouthén J, Helmersson S, Chawla R
Effects of void uncertainties on the void reactivity coefficient and pin power distributions for a 10 × 10 BWR assembly
Annals of Nuclear Energy. 2006; 33(2): 119-125. https://doi.org/10.1016/j.anucene.2005.09.007
DORA PSI
Jatuff F, Macku K, Chawla R
On the accuracy of reactor physics calculations for square HPLWR fuel assemblies
Annals of Nuclear Energy. 2006; 33(2): 198-207. https://doi.org/10.1016/j.anucene.2005.09.006
DORA PSI
Kuijper JC, Raepsaet X, de Haas JBM, von Lensa W, Ohlig U, Ruetten H-J, et al.
HTGR reactor physics and fuel cycle studies
Nuclear Engineering and Design. 2006; 236(5-6): 615-634. https://doi.org/10.1016/j.nucengdes.2005.10.021
DORA PSI
Lucas D, Krepper E, Prasser H-M, Manera A
Investigations on the stability of the flow characteristics in a bubble column
Chemical Engineering and Technology. 2006; 29(9): 1066-1072. https://doi.org/10.1002/ceat.200600150
DORA PSI
Ma W, Bubelis E, Karbojian A, Sehgal BR, Coddington P
Transient experiments from the thermal-hydraulic ADS lead bismuth loop (TALL) and comparative TRAC/AAA analysis
Nuclear Engineering and Design. 2006; 236(13): 1422-1444. https://doi.org/10.1016/j.nucengdes.2006.01.006
DORA PSI
Macku K, Jatuff F, Murphy MF, Joneja OP, Bischofberger R, Chawla R
Advanced foil activation techniques for the measurement of within-pin distributions of the ⁶³Cu(n,γ)⁶⁴Cu reaction rate in nuclear fuel
Nuclear Instruments and Methods in Physics Research, Section A: Accelerators, Spectrometers, Detectors and Associated Equipment. 2006; 562(1): 393-400. https://doi.org/10.1016/j.nima.2006.03.004
DORA PSI
Mikityuk K, Coddington P, Bubelis E, Chawla R
Comparison of the transient behaviour of LBE-and gas-cooled experimental accelerator-driven systems
Nuclear Engineering and Design. 2006; 236(23): 2452-2473. https://doi.org/10.1016/j.nucengdes.2006.03.012
DORA PSI
Murphy MF, Jatuff F, Grimm P, Seiler R, Brogli R, Meier G, et al.
Reactivity and neutron emission measurements of highly burnt PWR fuel rod samples
Annals of Nuclear Energy. 2006; 33(9): 760-765. https://doi.org/10.1016/j.anucene.2006.04.003
DORA PSI
Paratte JM, Früh R, Kasemeyer U, Kalugin MA, Timm W, Chawla R
A benchmark on the calculation of kinetic parameters based on reactivity effect experiments in the CROCUS reactor
Annals of Nuclear Energy. 2006; 33(8): 739-748. https://doi.org/10.1016/j.anucene.2005.09.012
DORA PSI
Pelloni S, Bubelis E, Mikityuk K, Coddington P
Calculations of reactivity-initiated transients in gas-cooled fast reactors using the code system fast
Annals of Nuclear Energy. 2006; 33(6): 499-509. https://doi.org/10.1016/j.anucene.2006.01.002
DORA PSI
Pelloni S, Coddington P
On using alternative perturbation theory methodologies in the evaluation of reactivity effects in ADS cores
Annals of Nuclear Energy. 2006; 33(17-18): 1360-1367. https://doi.org/10.1016/j.anucene.2006.10.001
DORA PSI
Plaschy M, Jatuff F, Grimm P, Tani F, Jacot-Guillarmod R, Giust F, et al.
Comparisons of deterministic neutronic calculations with Monte Carlo results for an advanced BWR fuel assembly with hafnium control blades
Journal of Nuclear Science and Technology. 2006; 43(11): 1298-1310. https://doi.org/10.3327/jnst.43.1298
DORA PSI
Romano A, Li J, Yip S
Atomistic simulation of rapid compression of fractured silicon carbide
Journal of Nuclear Materials. 2006; 352(1-3): 22-28. https://doi.org/10.1016/j.jnucmat.2006.02.038
DORA PSI
Romano A, Wallin H, Zimmermann MA, Chawla R
Modelling the CABRI high-burnup RIA test CIP0-1 using an extended version of the FALCON code
Nuclear Engineering and Design. 2006; 236(3): 284-294. https://doi.org/10.1016/j.nucengdes.2005.08.007
DORA PSI
Tani F, Jatuff F, Chawla R
Study of spectral heterogeneities for the interpretation of calculational trends in predicting pin power distributions in a SVEA-96+ BWR assembly
Annals of Nuclear Energy. 2006; 33(6): 490-498. https://doi.org/10.1016/j.anucene.2006.02.005
DORA PSI
Wenger HU, Al Mazouzi A, Atchison F, Burghartz M, Chawla R, Günther-Leopold I, et al.
Isobaric production cross sections from 0.6 GeV proton irradiation of neptunium and thorium using mass spectrometry
Nuclear Physics A. 2006; 764: 1-14. https://doi.org/10.1016/j.nuclphysa.2005.08.023
DORA PSI
Zilio VO, Joneja OP, Popowski Y, Rosenfeld A, Chawla R
Absolute depth-dose-rate measurements for an ¹⁹²Ir HDR brachytherapy source in water using MOSFET detectors
Medical Physics. 2006; 33(6): 1532-1539. https://doi.org/10.1118/1.2198168
DORA PSI

Operation Conditions Of A Phase Doppler Anemometer: Droplet Size Measurements With Laser Beam Power, Photomultiplier Voltage, Signal Gain And Signal-To-Noisle Ratio As Parameters
R Kapulla, SB Najera
Measurement Science & Technology 17, 221-227 (2006).
http://dx.doi.org/10.1088/0957-0233/17/1/034

Simulating Large-Scale Bubble Plumes Using Various Closure And Two-Phase Turbulence Models
R Zboray, Cachard de,
Nuclear Engineering And Design 235, 867-884 (2005).
http://dx.doi.org/10.1016/j.nucengdes.2004.11.008

Experimental Investigation Of Natural-Circulation Flow Behavior Under Low-Power/Low-Pressure Conditions In The Large-Scale Panda Facility
O Auban, D Paladino, R Zboray
Nuclear Technology 148, 294-312 (2004).
http://dx.doi.org/10.13182/NT04-A3568

Decobi: Investigation Of Melt Coolability With Bottom Coolant Injection
D Paladino, SA Theerthan, BR Sehgal
Progress In Nuclear Energy 40, 161-206 (2002).
http://dx.doi.org/10.1016/S0149-1970(01)00022-1

Study Of The Pwr Rea Pulse Width For Realistic Uo2 And Mox Core Designs Using 3-D Kinetics
H. Ferroukhi, M.A. Zimmermann
Annals of Nuclear Energy, Volume 36, Issue 8, Pp. 1170-1183, August 2009

Advanced Microchannel Heat Exchanger With S-Shaped Fins
N. Tsuzuki, Y. Kato, K. Nikitin, T. Ishizuka
Journal of Nuclear Science And Technology, 46(5), 403-412 (2009)

Sbloca With Boron Dilution In Pressurized Water Reactors. Impact On Operation And Safety
J. Freixa, F. ReventóS, C. Pretel, L. Batet, I. Sol
Nuclear Engineering and Des. (Issn 0029-5493), 239(4), 749-760 (2009)

AgInCd control rod failure in the QUENCH-13 bundle test
L. Sepold, T.M. Lind, A.P. Csordas, U. Stegmaier, M. Steinbrück, J. Stuckert
Annals of Nuclear Energy 36, 1349
http://dx.doi.org/10.1016/j.anucene.2009.06.020

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
Annals of Nuclear Energy* 36, 183
http://dx.doi.org/10.1016/j.anucene.2008.11.024

Potential steam generator tube rupture in the presence of severe accident thermal challenge and tube flaws due to foreign object wear
Y. Liao, S. Güntay
Nuclear Engineering and Design 239, 1128
http://dx.doi.org/10.1016/j.nucengdes.2009.02.003

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
Nuclear Engineering and Design 239, 244
http://dx.doi.org/10.1016/j.nucengdes.2008.10.017

A Generalized Mean Temperature Difference Method For Thermal Design Of Heat Exchangers
M. Utamura, K. Nikitin, Y. Kato
Ijnest, 4(1), (2008)

Steam Condensing Liquid Co2 Boiling Heat Transfer In A Steam Condenser For A New Heat Recovery System
K. Nikitin, Y. Kato, T. Ishizuka
International Journal of Heat And Mass Transfer, 51(17/18), 4544-4550 (2008)

Uncertainty And Sensitivity Analysis Of The Loft L2-5 Test: Results Of The Bemuse Programme
De CréCy A., Bazin P., Glaeser H., Skorek T., Joucla J., Probst P., Fujioka K., Chung B.D., Oh D.Y., Kyncl M., Pernica R., Macek J., Meca R., Macian R., D’Auria F. Petruzzi A. Bater L., Perez M., Reventos F.
Nuclear Engineering and Des. (Issn 0029-5493), 238, 3561-3578 (2008)

X-Ray Absorption Spectra Of Hexagonal Ice And Liquid Water By All-Electron Gaussian And Augmented Plane Wave Calculations
M. Iannuzzi-Mauri
J. Chem. Phys. (Issn 0021-9606), 128, 204506-204506-12 (2008)

First-Principles Molecular Dynamics Study Of The Heterogeneous Reduction Of No2 On Soot Surfaces
Rodriguez-Fortea A., Iannuzzi Mauri M.
J. Phys. Chem C (Issn 1932-7447), 112, 19642-19648 (2008)

Modeling Bulk And Surface Pt Using The “Gaussian And Plane Wave” Density Functional Theory Formalism: Validation And Comparison To K-Point Plane Wave Calculations
G. Santarossa, A. Vargas, Mauri. Iannuzzi, Pignedoli. M, A. C, D. Passerone, A. Baiker
J. Chem. Phys. (Issn 0021-9606), 129, 234703-234703-12 (2008)

Chiral Recognition On Catalytic Surfaces: Theoretical Insight In A Biomimetic Heterogeneous Catalytic System
A. Vargas, G. Santarossa, Mauri. Iannuzzi, Baiker. M,
J. Phys. Chem C (Issn 1932-7447), 112, 10200-10208 (2008)

Effects of chlorine and sulphur on particle formation in wood combustion performed in a laboratory scale reactor
O. Sippula, T.M. Lind, J.K. Jokiniemi
Journal of Fuel 87, 2425
http://dx.doi.org/10.1016/j.fuel.2008.02.004

A simple probabilistic approach to evaluate radioiodine behavior at severe accidents: Application to PHEBUS test FPT1
A. Rýdl
Nuclear Engineering and Design* 238, 2387
http://dx.doi.org/10.1016/j.nucengdes.2008.02.027

Accident management following loss of residual heat removal during mid-loop operation in a Westinghouse two-loop PWR
J.C. Birchley, T.J. Haste, M. Richner
Nuclear Engineering and Design 238, 2173
http://dx.doi.org/10.1016/j.nucengdes.2008.02.009

Validation of severe accident codes on the Phebus fission product tests in the framework of the PHEBEN-2 project
K. Müller, S. Dickinson, C. de Pascale, N. Girault, L.E. Herranz, F. de Rosa, G. Henneges, J. Langhans, C. Housiadas, V. Wichers, A. Dehbi, S. Paci, F. Martin-Fuentes, I. Turcu, I. Ivanov, B. Toth, L.G. Horvath
Nuclear Technology 163, 209

Bwr Stability And Bifurcatio Analysis Using Reduced Order Models And System Codes: Identification Of A Subcritical Hop Bifurcation Using Ramona
A. Dokhane, D. Hennig, Rizwan-Uddin, R. Chawla
Annals of Nuclear Energy, Volume 34, Issue 10, October 2007, Pp 792-802 (2007)

Experimental Investigation On Bublbe Turbulent Diffusion In A Vertical Large-Diameter Pipe By Wire-Mesh Sensors And Correlation Techniques
A. Manera, H-M. Prasser, D. Lucas
Nuclear Technology, 158(2), 291-303 (2007)

Fine particle and trace element emissions from waste combustion - Comparison of fluidized bed and grate firing
T.M. Lind, J. Hokkinen, J.K. Jokiniemi
Fuel Processing Technology 88, 737
http://dx.doi.org/10.1016/j.fuproc.2007.03.004

Major challenges to modeling aerosol retention near a tube breach during steam generator tube rupture sequences
L.E. Herranz, C. Lopez del Pra, A. Dehbi
Nuclear Technology 158, 83

Benchmark study on fuel bundle degradation in the Phebus FPT3 test using the severe accident codes ATHLET-CD, ICARE2, and MELCOR
B. Toth, K. Müller, J.C. Birchley, H. Wada, C. Jamond, K. Trambauer
Nuclear Technology 157, 132

Retran-3d Analysis Of The Base Case And The Four Extreme Cases Of The Oecd/Nea Peach Bottom 2 Turbine Trip Benchmark
W. Barten, P. Coddington, H. Ferroukhi
Annals of Nuclear Energy 33, Pp 99-118 (2006)

Spatial And Model-Order Based Reactor Signal Analysis Methodolgy For Bwr Core Stability Evaluation
A. Dokhane, H. Ferroukhi, M.A. Zimmermann, C. Aguirre
Annals of Nuclear Energy, Volume 33, Issue 16, November 2006, Pp 1329-1338 (2006)

Modeling The Cabri High-Burnup Ria Test Cip0-1 Using An Extended Version Of The Falcon Code
A. Romano, H. Wallin, M.A. Zimmermann, R. Chawla
Nuclear Engineering and Des. (Issn 0029-5493), 236, 284-294 (2006)

Implications Of Alternative Strategies For Transitions To Sustainable Fuel Cycles
A. Romano, T. Boscher, P. Hejzlar, M. Kazimi, N. Todreas
Nuclear Sci. Engineering and (Issn 0029-5639), 154, 1-27 (2006)

Effect of chlorine and sulfur on fine particle formation in pilot-scale CFBC of biomass
T.M. Lind, E.L. Kauppinen, J. Hokkinen, J.K. Jokiniemi, M. Orjala, M. Aurela, R. Hillamo
Energy and Fuels 20, 61
http://dx.doi.org/10.1021/ef050122i

Electrostatic precipitator performance and trace element emissions from two Kraft recovery boilers
T.M. Lind, J. Hokkinen, J.K. Jokiniemi, R. Hillamo, U. Makkonen, A. Raukola, J. Rintanen, K. Saviharju
Environmental Science & Technology 40, 584
http://dx.doi.org/10.1021/es0503027

MELCOR/MACCS simulation of the TMI-2 severe accident and initial recovery phases, off-site fission product release and consequences
T.J. Haste, J.C. Birchley, E.G. Cazzoli, J. Vitazkova
Nuclear Engineering and Design 236, 1099
http://dx.doi.org/10.1002/j.nucengdes.2005.11.012

Semi-Analytical Bifurcation Analysis Of Two-Phase Flow In A Heated Channel
A. Dokhane, D. Hennig, R. Chawla, Rizwan-Uddin
Int. J. Bifurcation Chaos (Issn 0218-1274), 15, 2395-2409 (2005)

Review Of The Licensing Basis For Ria And Loca Transients In Light Of New Evidence On High Burnup Fuel Behavior
M. Zimmermann, Bart. A,
Chimia (Issn 0009-4293), 59, 950-956 (2005)

Open-Pore Organic Material for Retaining Radioactive I2 and CH3I
T. Hertzsch, C. Gervais, J. Hulliger, B.S. Jäckel, S. Güntay, H. Bruchertseifer, A. Neels
Advanced Functional Materials 16, 268
http://dx.doi.org/10.1002/adfm.200500245

Development of semi-automated system for preparation of Re-188 aqueous solutions of high and reproducible activity concentrations
B.S. Jäckel, R.C. Cripps, Güntay, H. Bruchertseifer
Applied Radiation and Isotopes 63, 299
http://dx.doi.org/10.1016/j.apradiso.2005.04.009

Iodine behaviour during a severe accident in a nuclear power plant
S. Güntay, R.C. Cripps, B.S. Jäckel, H. Bruchertseifer
Chimia 59, 957
http://dx.doi.org/10.2533/000942905777675453

Phebus-FP: Results and significance for plant safety in Switzerland
J.C. Birchley, T.J. Haste, H. Bruchertseifer, R.C. Cripps, S. Güntay, B.S. Jäckel
Nuclear Engineering and Design 235, 1607
http://dx.doi.org/10.1016/j.nucengdes.2005.02.018

Steam generator tube rupture (SGTR) scenarios
A. Auvinen, J.K. Jokiniemi, A. Lahde, T. Routamo, P. Lundstrom, H. Tuomisto, J. Dienstbier, S. Güntay, D.J. Suckow, A. Dehbi, M. Slootman, L.E. Herranz, V. Peyres, J. Polo
Nuclear Engineering and Design 235, 457
http://dx.doi.org/10.1016/j.nucengdes.2004.08.060

European expert network for the reduction of uncertainties in severe accident safety issues (EURSAFE)
D. Magallon, A. Mailliat, J.M. Seiler, K. Athken, H. Sjovall, S. Dickinson, J. Jakab, L. Meyer, M. Buerger, K. Trambauer, L. Fickert, B.R. Sehgal, Z. Hozer, J. Bagues, F. Martin-Fuentes, R. Zeyen, A. Annunziato, M. El-Shanawany, S. Güntay, C. Tinkler, B. Turland, L.E. Herranz
Nuclear Engineering and Design 235, 309
http://dx.doi.org/10.1016/j.nucengdes.2004.08.042

On the radiolytic decomposition of colloidal silver iodide in aqueous suspension
S. Güntay, R.C. Cripps, B.S. Jäckel, H. Bruchertseifer
Nuclear Technology 150, 303

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2001 - 2004

Void Fraction And Critical Power Assessment Of Coretran-01/Vipre-02
Y. Aounallah
Nuclear Technol. (Issn 0029-5450), 145, 163-176 (2004)

Peach Bottom Bwr Turbine Trip Benchmark Analyses With Retran-3d And Coretran
W. Barten, H. Ferroukhi, P. Coddington
Nuclear Sci. Engineering and (Issn 0029-5639), 146, 306-324 (2004)

ARTIST: introduction and first results
S. Güntay, D.J. Suckow, A. Dehbi, R. Kapulla
Nuclear Engineering and Design 231, 109
http://dx.doi.org/10.1016/j.nucengdes.2004.02.012

The Analysis Of Pwr And Bwr Reactivity Transients With Coretran And Retran-3d
H. Ferroukhi, P. Coddington
Nuclear Technology, 142, 19-34 (2003)

Comparison Of Various Partial Light Water Reactor Core Loadings With Inert Matrix And Mixed-Oxide Fuel
U. Kasemeyer, Ch. Hellwig, J. Lebenhaft, R. Chawla
Journal of Nuclear Materials, 319, 142-153 (2003)

Assessment Of Retran-3d Boiling Models Against Experimental Subcooled Boiling Tube Data
R. Macian, P. Coddington, P. Stangroom
Nuclear Technology, Vol. 142, 47-63 (2003)

Interpretation Of Experimental Results From Moderate-Power In-Pile Testing Of A Pu-Er-Zr-Oxide Inert Matrix Fuel
Hellwig Ch., Kasemeyer U., Ledergerber G., Byung-Ho Lee, Young-Woo Lee, Chawla R.
Annals of Nuclear Energy 30, 287-299 (2003)

Planned Experimental Studies On Natural Circulation And Stability Performance Of Boiling Water Reactors In Four Experimental Facilities And First Results (Nacusp
De Kruijf W.J.M., Katelaar K.C.J, Avakian G., Gubernatis P., Caruge D., Manera A., Van Der Hagen T.H.J.J., Yadigaroglu G., Domenicus G., Rohde U., Prasser H.-M., Castrillo F., Huggenberger M., Hennig D., Munoz-Cobo J.L., Aguirre C.
Nuclear Engineering And Design, 221, 241-250 (2003)

Analysis of iodine species in aqueous solutions
H. Bruchertseifer, R.C. Cripps, S. Güntay, B.S. Jäckel
Analytical and Bioanalytical Chemistry 375, 1107
http://dx.doi.org/10.1007/s00216-003-1779-3

Fission product iodine release and retention in nuclear reactor accidents - experimental programme at PSI
H. Bruchertseifer, R.C. Cripps, S. Güntay, B.S. Jäckel
Czechoslovak Journal of Physics 53, 611
http://dx.doi.org/10.1007/s10582-003-0079-7

Electrostatic precipitator collection efficiency and trace element emissions from co-combustion of biomass and recovered fuel in fluidized-bed combustion
T.M. Lind, J. Hokkinen, J.K. Jokiniemi, S. Saarikoski, R. Hillamo
Environmental Science & Technology 37, 2842
http://dx.doi.org/10.1021/es026314z

Validation of severe accident codes against Phebus FP for plant applications: status of the PHEBEN2 project
A.V. Jones, 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-Fuentes
Nuclear Engineering and Design 221, 225
http://dx.doi.org/10.1016/S0029-5493(02)00340-0

Core loss during a severe accident (COLOSS)
B. Adroguer, P. Chatelard, J.P. van Dorsselaere, C. Duriez, N. Cocuaud, L. Bellenfant, D. Bottomley, V. Vrtilkova, K. Müller, W. Hering, C. Homann, W. Krauss, A. Miassoedov, M. Steinbrück, J. Stuckert, Z. Hozer, G. Bandini, J.C. Birchley, T. von Berlepsch, M. Buck, J.A.F. Benitez, E. Virtanen, S. Marguet, G. Azarian, H. Plank, M. Veshchunov, Y. Zvonarev, A. Goryachev
Nuclear Engineering and Design 221, 55
http://dx.doi.org/10.1016/S0029-5493(02)00344-8

Analysis And Sensitivity Studies Of Postulated Sb-Locas In The MüHleberg (Kkm) Bwr/4 By Trac-Bf1
G. Analytis, Coddington. Th,
Annals of Nuclear Energy, 29, 1525-1549 (2002)

A Novel Auto-Correlation Function Method For The Determination Of The Decay Ratio In Bwr Stability Analysis
K. Behringer, D. Hennig
Annals of Nuclear Energy, 29, 1483-1504 (2002)

A Study Of The Performance Of Void Fraction Correlations Used In The Context Of Drift-Flux Two-Phase Flow Models
P. Coddington, R. Macian
Nuclear Engineering And Design, 215, 199-216

Application And In-Depth Assessment Of Retran-3d For Best Estimate Analysis Of Nuclear Power Plant Transients
P. Coddington, R. Macian, M. Zimmermann, Chawla. A,
Journal of Nuclear Science And Technology, 39-9, 972-985 (2002)

Simulation And Analysis Of Experimental Blow Down And Small-Break Loss-Of-Coolant Scenarios With Retran-3d
R. Macian, P. Coddington
Nuclear Technology, Vol. 139, 185-204 (2002)

A Nodal Modal Method For The Neutron Diffusion Equation. Application To Bwr Stability Analysis
R. Miro, D. Ginestar, G. Verdu, D. Hennig
Annals of Nuclear Energy, 29, 1171-1194 (2002)

On The Feasibility Of Ads-Representative Integral Experiments Using Limited Amounts Of Low-Enriched U-Fuel
S. Pelloni, R. Chawla
Journal of Nuclear Science And Technology, Supplement 2, 1224-1227 (2002)

Data Sensitivity Of Design Calculations For High Conversion D2o Reactors
S. Pelloni, H. Hager, O. Joneja, Chawla. P,
Journal of Nuclear Science And Technology, Supplement 2, 880-883 (2002)

The Physical Mechanism Of Core-Wide And Local Instabilities At The Forsmark-1 Bwr
G. Analytis, Hennig. Th, H. D, K. Karlsson,
Nuclear Engineering And Design, Vol. 205, Pp. 91-105, 2001.

Containment behaviour in the event of core melt with gaseous and aerosol releases (CONGA)
E. Friesen, J. Meseth, S. Güntay, D.J. Suckow, J.L. Jimenez, L.E. Herranz, V. Peyres, G.F. De Santi, A. Krasenbrink, M. Valisi, L. Mazzochi
Nuclear Engineering and Design 209, 253
http://dx.doi.org/10.1016/S0029-5493(01)00408-3

Aerosol retention in low-subcooling pools under realistic accident conditions
A. Dehbi, D.J. Suckow, S. Güntay
Nuclear Engineering and Design 203, 229
http://dx.doi.org/10.1016/S0029-5493(00)00343-5

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2000 and before

A Study Of Boiling Water Reactor Stability Behaviour
D. Hennig
Nuclear Technology, Vol. 126, Pp 10-31, (1999)

Implementation Of An Improved Interfacial Mass And Energy Transfer Model In Retran-3d
R. Macian, P. Cebull, P. Coddington, M. Paulsen
Nuclear Technology, Vol. 128, Pp 139-152, (1999)

Evaluation Of The Slip Option In Retran-3d
D. Maier, P. Coddington
Nuclear Technology, Vol. 128, Pp 153-168, (1999)

Vipre-02 Subchannel Validation Against Nupec Bwr Void Fraction Data
Y. Aounallah, P. Coddington
Nuclear Technology, Vol. 128, Pp 225-232, (1999)

Field study on ash behavior during circulating fluidized-bed combustion of biomass. 2. Ash deposition and alkali vapor condensation
T. Valmari, T.M. Lind, E.I. Kauppinen, G. Sfiris, K. Nilsson, W. Maenhaut
Energy & Fuels 13, 390
http://dx.doi.org/10.1021/ef9800866

Field study on ash behavior during circulating fluidized-bed combustion of biomass. 1. Ash formation
T. Valmari, T.M. Lind, E.I. Kauppinen, G. Sfiris, K. Nilsson, W. Maenhaut
Energy & Fuels 13, 379
http://dx.doi.org/10.1021/ef980085d

Volatilization of the heavy metals during circulating fluidized bed combustion of forest residue
T.M. Lind, T. Valmari, E.I. Kauppinen, G. Sfiris, K. Nilsson, W. Maenhaut
Environmental Science & Technology 33, 496
http://dx.doi.org/10.1021/es9802596

Core melt down and vessel failure: a coupled problem
G. Duijvestijn, J.C. Birchley
Nuclear Engineering and Design 191, 17
http://dx.doi.org/10.1016/S0029-5493(99)00050-3

Prediction of thermoplastic failure of a reactor pressure vessel under a postulated core melt accident
G. Duijvestijn, J.C. Birchley, K. Reichlin
Computers & Structures 64, 1239
http://dx.doi.org/10.1016/S0045-7949(97)00032-1

A model for the performance of a vertical tube condenser in the presence of noncondensable gases
A. Dehbi, S. Güntay
Nuclear Engineering and Design 177, 41
http://dx.doi.org/10.1016/S0029-5493(97)00184-2

CORVIS. Investigation of light water reactor lower head failure modes
S. Brosi, G. Duijvestijn, H. Hirschmann, B.S. Jäckel, K. Nakada, J.A. Patorski, R. Rösel, H.P. Seifert, P. Tipping
Nuclear Engineering and Design 168, 77
http://dx.doi.org/10.1016/S0029-5493(96)00008-8

Ash vaporization in circulating fluidized bed coal combustion
T.M. Lind, E.I. Kauppinen, W. Maenhaut, A. Shah, F. Huggins
Aerosol Science and Technology 24, 135
http://dx.doi.org/10.1080/02786829608965359

Fuel-Temperature Coefficient For Boiling Water Reactor Transient Calculations: Its Dependence On Reactor Conditions
J.M. Kallfelz, L.A. Belblidia, P. Grimm
Nuclear Science And Engineering 121 (1995), 301-311

CORVIS - Researching Reactor Pressure-Vessel Melt Through
H. Hirschmann, J.P. Hosemann, B.S. Jäckel
Nuclear Engineering International 40, 34

Cross-Sections of Proton-Induced Nuclear-Reactions on Enriched Cd-111 and Cd-112 for the Production of In-111 for use in Nuclear-Medicine
F. Tarkanyi, F. Szelecsenyi, P. Kopecký, T. Molnar, L. Ando, P. Mikecz, G. Toth, A. Rýdl
Applied Radiation and Isotopes 45, 239
http://dx.doi.org/10.1016/0969-8043(94)90018-3

Study of Size-Fractionated Coal-Combustion Aerosols using Instrumental Neutron-Activation Analysis
W. Maenhaut, E.I. Kauppinen, T.M. Lind
Journal of Radioanalytical and Nuclear Chemistry - Articles 167, 259
http://dx.doi.org/10.1007/BF02037185

Analysis of Size-Fractionated Coal Combustion Aerosols by PIXE and other Analytical Techniques
W. Maenhaut, O. Royset, M. Vadset, E.I. Kauppinen, T.M. Lind
Nuclear Instruments and Methods in Physics Research Section B - Beam Interactions with Materials and Atoms 75, 266
http://dx.doi.org/10.1016/0168-583X(93)95656-P

Evaluation of Neutral Dialkoxy Dithiophosphate Complexes of Thallium-201 as Myocardial Perfusion Tracers
P. Kopecký, A. Rýdl, B. Kopecká, P. Švihovcová, K. Bakos
European Journal of Nuclear Medicine 18, 669

Aerosols from Circulating Fluidized-Bed Coal Combustion
E.I. Kauppinen, T.M. Lind, J.J. Eskelinen, J.K. Jokiniemi, W. Maenhaut, O. Royset, M. Vadset, H. Vilokki, R. Kuivalainen
Journal of Aerosol Science 22, 467
http://dx.doi.org/10.1016/S0021-8502(05)80139-9

Mass and Charge Flow in the reaction 7.1 MeV/u Au-197 + Cu-63
B.S. Jäckel, A. Rox, B.A. Esterlund, W. Westmaier, M. Knaack, P. Patzelt
Zeitschrift für Physik A-Hadrons and Nuclei 339, 475
http://dx.doi.org/10.1007/BF01288431

Dynamic Contributions to Symmetric Fragmentation Processes
H. Schulte, B.S. Jäckel, B.A. Esterlund, M. Knaack, W. Westmaier, A. Rox, P. Patzelt
Physics Letters B 232, 37
http://dx.doi.org/10.1016/0370-2693(89)90554-6

On the Photopeak Efficiency of Germanium Gamma-Ray Detectors
B.S. Jäckel, W. Westmaier, P. Patzelt
Nuclear Instruments & Methods in Physics Research Section A - Accelerators Spectrometers Detectors and associated Equipment 261, 543
http://dx.doi.org/10.1016/0168-9002(87)90367-6

Studies on the Biological Half-Life of Cesium in Roe Deer
D. Molzahn, J. van Aarle, A. Merklin, B.S. Jäckel, W. Westmaier, P. Patzelt
Zeitschrift für Jagdwissenschaft 33, 89
http://dx.doi.org/10.1007/BF02241758

Transient Evaporation and Combustion of a Composite Water-Oil Droplet
J.C. Birchley, N. Riley
Combustion and Flame* 29, 145
http://dx.doi.org/10.1016/0010-2180(77)90104-3

Droplet Combustion in a Stream of Oxidant
J.C. Birchley
Mathematical Physical and Engineering Sciences 347, 195
http://dx.doi.org/10.1098/rspa.1975.0205

Droplet Combustion in a Stream of Oxidant
J.C. Birchley
Mathematical Physical and Engineering Sciences 347, 195
http://dx.doi.org/10.1098/rspa.1975.0205

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