Conference Publications of the Experimental Thermal-Hydraulics Group

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

Please find here a selection of conferences:
 

  • PHYSOR - International Conference on Physics of Reactors
  • NURETH - International Topical Meeting on Nuclear Reactor Thermalhydraulics
  • M&C - International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering
  • ICONE - International Conference of Nuclear Engineering
  • NUTHOS - International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation and Safety
  • ANS Student Conference
  • ENYGF - European Nuclear Young Generation Forum

2024

  • Migliorini M, Zachos PK, Macmanus DG, Doll U, Dues M, Steinbock J, et al.
    Seeding-free inlet flow distortion measurements using filtered Rayleigh scattering: integration in a complex intake test facility
    In: AIAA SciTech forum and exposition, 2024. Reston: American Institute of Aeronautics and Astronautics; 2024:AIAA 2024-2831 (17 pp.). https://doi.org/10.2514/6.2024-2831
    DORA PSI
  • Vocke M, Kapulla R, Morton C, Martinuzzi RJ
    Augmenting PIV temporal resolution via semi-Lagrangian estimation of velocity fluctuations
    In: Örlü R, Talamelli A, Peinke J, Oberlack M, eds. Progress in turbulence X. Proceedings of the iTi conference on turbulence 2023. Vol. 404. Springer proceedings in physics. Cham: Springer Nature; 2024:197-203. https://doi.org/10.1007/978-3-031-55924-2_26
    DORA PSI
  • Vocke M, Kapulla R, Morton C, Martinuzzi R
    Augmenting PIV temporal resolution via semi-Lagrangian estimation of velocity fluctuations
    In: Örlü R, Talamelli A, Peinke J, Oberlack M, eds. Progress in turbulence X. Proceedings of the iTi conference on turbulence 2023. Vol. 404. Springer proceedings in physics; 1066. Cham: Springer; 2024:197-203.
    DORA PSI

 

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2023

  • Chae M-S, Paladino D, Kelm S
    Analyses of jet-buoyant flow in a multi-compartment containment using an open-source solver
    In: 20th international topical meeting on nuclear reactor thermal hydraulics (NURETH-20). Illinois: American Nuclear Society; 2023:4059-4072. https://doi.org/10.13182/NURETH20-40154
    DORA PSI
  • Dehbi A, Kapulla R
    CFD simulations of large-scale tests highlighting the effects of thermal radiation in steam-containing atmospheres
    Presented at: https://doi.org/10.13182/NURETH20-40250
    DORA PSI
  • Doll U, Kapulla R, Steinbock J, Dues M, Migliorini M, Zachos PK
    Seeding-free inlet flow distortion measurement by filtered Rayleigh scattering: diagnostic approach and verification
    In: AIAA SCITECH 2023 forum. Reston: American Institute of Aeronautics and Astronautics; 2023:714-725. https://doi.org/10.2514/6.2023-1372
    DORA PSI
  • Faldella F, Eisenring S, Kim T, Doll U, Jansohn P
    Turbulent flame speed and flame characteristics of lean premixed H2-CH4 flames at moderate pressure levels
    In: Proceedings of ASME Turbo Expo 2023: turbomachinery technical conference and exposition. Vol. 3A. Turbo expo: power for land, sea and air. New York: American Society of Mechanical Engineers ASME; 2023:V03AT04A068 (10 pp.). https://doi.org/10.1115/gt2023-102527
    DORA PSI
  • Kim T, Doll U, Faldella F, Jansohn P
    Quantification of mixing quality effects on flashback limits for H2-rich fuel gases
    In: Proceedings of ASME turbo expo 2023: turbomachinery technical conference and exposition (GT2023). Vol. 3A. Proceedings of the ASME turbo expo. New York: American Society of Mechanical Engineers ASME; 2023:(9 pp.). https://doi.org/10.1115/gt2023-101551
    DORA PSI
  • Paladino D, Kapulla R, Chae MS, Paranjape S, Mignot G, Kudinov P
    PANDA experiment addressing the thermal effects in a large water pool caused by steam and a lighter non-condensable gas release from a multi-hole sparger
    In: 20th international topical meeting on nuclear reactor thermal hydraulics (NURETH-20). Illinois: American Nuclear Society; 2023:4006-4019. https://doi.org/10.13182/NURETH20-40388
    DORA PSI

 

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2022

  • Doll U, Röhle I, Dues M
    Unsteady multi-parameter flow diagnostics by filtered Rayleigh scattering: system design by multi-objective optimisation
    In: Proceedings of the 20th international symposium on the application of laser and imaging techniques to fluid mechanics. ; 2022:(18 pp.).
    DORA PSI
  • Liu X, Kelm S, Kampili M, Allelein H-J, Kapulla R, Paladino D, et al.
    Validation of a finite volume Monte Carlo solver for nongray gas radiation in containment flows
    In: 19th international topical meeting on nuclear reactor thermal hydraulics (NURETH-19). Illinois: American Nuclear Society; 2022:19001 (16 pp.).
    DORA PSI
  • Miniero L, Pandey K, Shcherbanev S, Doll U, Noiray N
    Effects of the atomization air on the topology of a Jet A-1 spray flame in a turbulent vitiated crossflow
    In: 10th European combustion meeting proceedings. Naples: mcm; 2022:1270-1275.
    DORA PSI
  • Miniero L, Pandey K, Shcherbanev S, Noiray N, Doll U
    Tomographic reconstruction of OH density maps for Jet-A1 spray flame in a vitiated crossflow
    In: AIAA scitech forum 2022. Reston, VA: American Institute of Aeronautics and Astronautics; 2022:AIAA 2022-1873 (8 pp.). https://doi.org/10.2514/6.2022-1873
    DORA PSI
  • Shcherbanev S, Morinière T, Solana-Pérez R, Doll U, Noiray N
    Flame anchoring of a premixed jet flame in vitiated crossflow using nanosecond repetitively pulsed discharge
    In: 10th European combustion meeting proceedings. Naples: mcm; 2022:1425-1429. https://www.ecm2021napoli.eu/proceedings/.
    DORA PSI
  • Vázquez-Rodríguez C, Jiménez G, Andreani M, Paladino D, Paranjape S, Kapulla R, et al.
    Simulation of PANDA PE1 spray test using GOTHIC 8.3(QA)
    In: 19th international topical meeting on nuclear reactor thermal hydraulics (NURETH-19). Illinois: American Nuclear Society; 2022:35515 (16 pp.).
    DORA PSI

 

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2021

No Conference Articles in 2021

2020

No Conference Articles in 2020

2019

  • Andreani M, Paranjape S
    Modelling of the interaction of two heat sources simulating the thermal effects of PARs
    Presented at: ICAPP 2019 - International congress on advances in nuclear power plants; May 12-15, 2019; Juan-les-pins, France.
    DORA PSI
  • Falsetti C, Kapulla R, Paranjape S, Paladino D
    Thermal radiation effect on thermocouple measurements
    In: SWINTH-2019. Specialists workshop on advanced instrumentation and measurement techniques for experiments related to nuclear reactor thermal hydraulics and severe accidents. sine loco: sine nomine; 2019:054 (11 pp.).
    DORA PSI
  • Gallego-Marcos I, Villanueva W, Kapulla R, Paranjape S, Paladino D, Kudinov P
    Modeling of thermal stratification and mixing induced by steam injection through spargers into a large water pool
    In: Computational fluid dynamics for nuclear reactor safety applications-6 (CFD4NRS-6). Workshop proceedings. sine loco: OECD; NEA; 2019:(17 pp.).
    DORA PSI
  • Kapulla R, Paranjape S, Falsetti C, Paladino D
    High spatial resolution PIV measurements in the PANDA facility
    Presented at: ICAPP 2019 - international congress on advances in nuclear power plants; May 12-15, 2019; Juan-les-pins, France.
    DORA PSI
  • Paranjape S, Kapulla R, Mignot G, Paladino D
    Gas redistribution caused by interacting sources in the presence of a vertical condenser
    Presented at: ICAPP 2019 - international congress on advances in nuclear power plants; May 12-15, 2019; Juan-les-pins, France.
    DORA PSI
  • Wolfertz A, Adams R, Perret G
    First tests of a gamma-blind fast neutron detector prototype based on ZnS and wavelength-shifting fibers
    In: Annual meeting 2019. Vol. 120. Transactions of the American Nuclear Society. La Grange Park: American Nuclear Society; 2019:426-428.
    DORA PSI

 

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2018

  • Andreani M, Kapulla R
    Analyses of gas stratification erosion by a vertical jet in presence of an obstacle using the GOTHIC code
    In: Proceedings of the 26th international conference on nuclear engineering (ICONE26). Thermal hydraulics and safety analyses. Vol. 6B. New York: American Society of Mechanical Engineers (ASME); 2018:ICONE26-82360 (11 pp.). https://doi.org/10.1115/ICONE26-82360
    DORA PSI
  • Kromer H, Adams R, Soubelet B, Zboray R, Prasser HM
    Improvement of a compact fast neutron generator for imaging applications
    In: 2018 IEEE nuclear science symposium and medical imaging conference proceedings (NSS/MIC). sine loco: IEEE; 2018:(3 pp.). https://doi.org/10.1109/NSSMIC.2018.8824470
    DORA PSI

 

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2017

  • Hursin M, Leray O, Perret G, Pautz A, Bostelmann F, Aures A, et al.
    Impact of implicit effects on uncertainties and sensitivities of the Doppler coefficient of a LWR pin cell
    In: Plompen A, Hambsch F-J, Schillebeeckx P, Mondelaers W, Heyse J, Kopecky S, et al., eds. ND 2016: international conference on nuclear data for science and technology. Vol. 146. EPJ web of conferences. sine loco: EDP Sciences; 2017:09034 (5 pp.). https://doi.org/10.1051/epjconf/201714609034
    DORA PSI
  • Moretti F, D’Auria F, Aksan N, Lutsanych S, Umminger K, Gupta S, et al.
    Summary of SWINTH-2016: a specialists workshop on advanced instrumentation and measurement techniques for nuclear reactor thermal-hydraulics experimentation
    In: 17th international topical meeting on nuclear reactor thermal hydraulics (NURETH-17). Vol. 5. Association for Computing Machinery, Inc; 2017:2531-2545.
    DORA PSI
  • Palmiotti G, Salvatores M, Hursin M, Kodeli I, Gabrielli F, Hummel A
    New approaches to provide feedback from nuclear and covariance data adjustment for effective improvement of evaluated nuclear data files
    In: Plompen A, Hambsch F-J, Schillebeeckx P, Mondelaers W, Kopecky S, Siegler P, et al., eds. ND 2016: international conference on nuclear data for science and technology. Vol. 146. EPJ web of conferences. sine loco: EDP Sciences; 2017:06003 (11 pp.). https://doi.org/10.1051/epjconf/201714606003
    DORA PSI

Monte Carlo Simulation Of Scintillation Detector For Spent Fuel Characterization In A Hot Cell
M Papadionysiou, G Perret, R Zboray, R Adams
Ans Student Conference 2017, April 6-9, 2017, Pittsburgh, Pa, Usa , (2017).

 

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2016

  • Andreani M, Daqiang Y, Gaikwad AJ, Ganju S, Gera B, Grigoryev S, et al.
    Synthesis of a blind CFD benchmark exercise based on a test in the PANDA facility addressing the stratification erosion by a vertical jet in presence of a flow obstruction
    In: Computational fluid dynamics for nuclear reactor safety applications-6 (CFD4NRS-6). Workshop proceedings. Paris: OECD; NEA; 2016:(13 pp.).
    DORA PSI
  • Grimm P, Hursin M, Perret G, Siefman D, Ferroukhi H
    CASMO-5 analysis of reactivity worths of burnt PWR fuel samples measured in LWR-proteus PHASE II
    In: Physics of reactors 2016 (PHYSOR 2016). Unifying theory and experiments in the 21st century. LaGrange Park, IL, USA: American Nuclear Society; 2016:2518-2527.
    DORA PSI
  • Hursin M, Siefman D, Perret G, Grimm P, Pautz A
    Verification of the new implementations in SHARK-X for reactivity coefficients and relative reactivity worth UQ
    In: Physics of reactors 2016 (PHYSOR 2016). Unifying theory and experiments in the 21st century. LaGrange Park, IL, USA: American Nuclear Society; 2016:674-683.
    DORA PSI
  • Lamirand V, Hursin M, Frajtag P, Pautz A, Perret G, Pakari O
    Future experimental programmes in the CROCUS reactor
    In: Conference proceedings. Berlin, Germany. 13-17 March 2016. European research reactor conference 2016. Bruessels, Belgium: European Nuclear Society; 2016:284-291.
    DORA PSI
  • Mignot G, Dupont J, Paladino D, Prasser H-M
    Containment thermal-hydraulic experiment and potential for severe accident studies in the LINX facility
    Presented at: 11th international topical meeting on nuclear reactor thermal hydraulics, operation and safety (NUTHOS-11); October 9-13, 2016; Gyeongju, Korea.
    DORA PSI
  • Paranjape S, Kapulla R, Mignot G, Paladino D
    Erosion of a helium layer due to the flow resulting from the interaction of a steam jet with a flow obstruction in a large vessel
    Presented at: 11th international topical meeting on nuclear reactor thermal hydraulics, operation and safety (NUTHOS-11); October 9-13, 2016; Gyeongju, Korea.
    DORA PSI
  • Perret G
    Delayed neutron fraction and prompt decay constant measurement in the Minerve reactor using the PSI instrumentation
    In: 2015 4th international conference on advancements in nuclear instrumentation measurement methods and their applications (ANIMMA). 2015 4th international conference on advancements in nuclear instrumentation measurement methods and their applications (ANIMMA). Danvers: IEEE; 2016:8 pp. https://doi.org/10.1109/ANIMMA.2015.7465533
    DORA PSI
  • Perret G, Vlassopoulos E, Hursin M, Pautz A
    Toward reanalysis of the tight-pitch HCLWR-PROTEUS Phase II experiments
    In: Serot O, ed. Wonder-2015 – 4th international workshop on nuclear data evaluation for reactor applications. Vol. 111. EPJ web of conferences. Les Ulis Cedex A, France: EDP Sciences; 2016:11006 (9 pp.). https://doi.org/10.1051/epjconf/201611111006
    DORA PSI
  • Rais A, Hursin M, Perret G, Pautz A
    Experimental validation of control rod reactivity worth and fission rate distributions for the CROCUS Reactor
    In: Physics of reactors 2016 (PHYSOR 2016). Unifying theory and experiments in the 21st century. Vol. 6. LaGrange Park, IL, USA: American Nuclear Society; 2016:3874-3883.
    DORA PSI

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

 

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2015

  • Andreani M, Badillo A, Kapulla R, Smith B
    Synthesis of the oECD/NEA-PSI CFD benchmark exercise
    In: 16th international topical meeting on nuclear reactor thermal hydraulics, NURETH 2016. Vol. 3. American Nuclear Society; 2015:1787-1801.
    DORA PSI
  • Hursin M, Joo HG, Downar TJ
    Assessment of thermal hydraulic feedbacks effects during modeling of a RIA using direct whole core transport solution
    In: Mathematics and computations, supercomputing in nuclear applications and Monte Carlo international conference (M&C and SNA and MC 2015). LaGrange Park, IL, USA: American Nuclear Society; 2015:2394-2405.
    DORA PSI
  • Hursin M, Rossinelli L, Ferroukhi H, Pautz A
    BWR full core analysis with SERPENT/SIMULATE-3 hybrid stochastic/determinstic code sequence
    In: Mathematics and computations, supercomputing in nuclear applications and Monte Carlo international conference (M&C and SNA and MC 2015). LaGrange Park, IL, USA: American Nuclear Society; 2015:1794-1806.
    DORA PSI
  • Kapulla R, Kelm S, Mignot G, Paranjape S, Paladino D
    Experimental and numerical results for the erosion dynamics of a vertical helium-air jet interacting with a helium rich layer
    In: Proceedings of ICAPP 2015. Vol. 49. INIS. Paris: SFEN; 2015:15242 (16 pp.). https://inis.iaea.org/search/search.aspx?num=10&orig_q=RN%3a49005001&lang=en-US&login=false&user=External&src=&sort=date:D:L:d1&sortorder=ascending&search-option=Everywhere&q=+inmeta:ConferenceTitle%3DICAPP%25202015%253A%2520Nuclear%2520Innovations%2.
    DORA PSI
  • Kelm' S, Kapulla R, Allelein HJ
    Erosion of a confined stratified layer by a vertical jet - detailed assessment of a CFD approach against the OECD/NEA PSI benchmark
    In: 16th international topical meeting on nuclear reactor thermal hydraulics (NURETH-16). Vol. 6. American Nuclear Society; 2015:4462-4475.
    DORA PSI
  • Mignot G, Paranjape S, Kapulla R, Paladino D
    Performance of hydrogen mitigation systems for a scaled accident scenario: overview of ERCOSAM project experimental results for the PANDA facility
    In: 16th international topical meeting on nuclear reactor thermal hydraulics (NURETH-16). LaGrange Park, IL, USA: American Nuclear Society; 2015:5456-5469.
    DORA PSI
  • Newman GR, Jordan KA, Perret G
    GCFR-PROTEUS experimental program benchmark analysis
    In: Uckan NA, Federici G, Michal R, Corradini ML, Tompkins B, Klein AC, et al., eds. Transactions of the American nuclear society. Vol. 113. Transactions of the American Nuclear Society. American Nuclear Society; 2015:186-189.
    DORA PSI
  • Paladino D, Kapulla R, Mignot G, Paranjape S
    Combined effects of cooler and spray activation on the hydrogen distribution in the presence of a jet flow
    In: 16th international topical meeting on nuclear reactor thermal hydraulics (NURETH-16). Vol. 2. American Nuclear Society; 2015:1502-1515.
    DORA PSI
  • Paladino D, Kiselev A
    Main outcomes from the EURATOM-ROSATOM ERCOSAM SAMARA parallel projects for hydrogen safety of LWR
    In: Proceedings of ICAPP 2015. Vol. 49. INIS. Paris: SFEN; 2015:15357 (11 pp.). https://inis.iaea.org/search/search.aspx?orig_q=RN:49004920.
    DORA PSI
  • Paranjape S, Kapulla R, Mignot G, Paladino D
    Parametric study on density stratification erosion caused by a horizontal steam jet interacting with a vertical plate obstruction
    In: 16th international topical meeting on nuclear reactor thermal hydraulics (NURETH-16). LaGrange Park, IL, USA: American Nuclear Society; 2015:4490-4503.
    DORA PSI
  • Zboray R, Dangendorf V, Mor I, Tittelmeier K, Bromberger B, Prasser H-M
    Time-resolved fast neutron radiography of air-water two-phase flows
    In: Lehmann EH, Kaestner AP, Mannes D, eds. Proceedings of the 10th world conference on neutron radiography (WCNR-10) Grindelwald, Switzerland October 5-10, 2014. Vol. 69. Physics procedia. sine loco: Elsevier; 2015:551-555. https://doi.org/10.1016/j.phpro.2015.07.078
    DORA PSI

 

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  • Dupont J, Mignot G, Zboray R, Prasser H-MP
    Characterization and validation of the near infrared film thickness profile technique
    Presented at: 10th international topical meeting on nuclear thermal-hydraulics, operation and safety (NUTHOS-10); December 14-18, 2014; Okinawa, Japan.
    DORA PSI
  • Grimm P, Perret G, Ferroukhi H
    CASMO-4E AND CASMO-5 analysis of the isotopic compositions of the LWR-PROTEUS phase II burnt PWR UO2 fuel samples
    Presented at: International conference on physics of reactors (PHYSOR 2014); September 28-October 3, 2014; Kyoto, Japan.
    DORA PSI
  • Hursin M, Ferroukhi H, Pautz A
    Neutronic Data Generation for BWR Models, Comparison OF SERPENT and CASMO-5
    Presented at: ANS student conference 2014; April 3-6, 2014; University Park, PA, USA.
    DORA PSI
  • Hursin M, Scriven M, Perret G, Grimm P, Pautz A
    Pinpower uncertainty quantification of LWR-PROTEUS phase III experiments
    Presented at: International conference on physics of reactors (PHYSOR 2014); September 28-October 3, 2014; Kyoto, Japan.
    DORA PSI
  • Hursin M, Siefman D, Rais A, Girardin G, Pautz A
    Verification of a reactor physics calculation scheme for the CROCUS reactor
    In: 3rd international technical meeting on small reactors. Vol. 1. Toronto, Canada: Canadian nuclear society; 2014. https://infoscience.epfl.ch/record/253153/files/ITSMR_2014.pdf.
    DORA PSI
  • Kapulla R, Mignot G, Paranjape S, Paladino D
    Stably stratified helium layer erosion by a vertical buoyant helium-air jet
    In: Proceedings of the 2014 international congress on advances in nuclear power plants. La Grange Park: American Nuclear Society; 2014:(23 pp.). https://www.ans.org/store/item-700385/.
    DORA PSI
  • Leray O, Grimm P, Hursin M, Ferroukhi H, Pautz A
    Uncertainty quantification of spent fuel nuclide compositions due to cross sections, decay constants and fission yields
    Presented at: International conference on physics of reactors (PHYSOR 2014); September 28-October 3, 2014; Kyoto, Japan.
    DORA PSI
  • Paladino D, Mignot G, Kapulla R, Paranjape S, Andreani M, Studer E, et al.
    OECD/NEA HYMERES project: for the analysis and mitigation of a severe accident leading to hydrogen release into a nuclear plant containment
    In: International congress on advances in nuclear power plants (ICAPP 2014). Vol. 2. Illinois: American Nuclear Society (ANS); 2014:1314-1322.
    DORA PSI
  • Paranjape S, Mignot G, Paladino D
    Effect of thermal stratification on full cone spray performance in reactor containment for a scaled scenario
    In: Proceedings of the 2014 22nd international conference on nuclear engineering (ICONE22). New York: American Society of Mechanical Engineers (ASME); 2014:V02BT09A020 (14 pp.). https://doi.org/10.1115/ICONE22-30755
    DORA PSI
  • Rais A, Siefman D, Girardin G, Hursin M, Pautz A
    PARCS few-group homogenized parameters generation using Serpent Monte Carlo code at the CROCUS reactor
    In: 16h meeting of the international group on research reactors. sine loco: IGORR; 2014:(11 pp.). https://www.igorr.com/Documents/2014-BARILOCHE/AdolfoRAIS-CROCUS.pdf.
    DORA PSI
  • Wicaksono D, Grimm P, Vasiliev A, Hursin M, Perret G, Ferroukhi H
    Validation of two Monte Carlo codes for LWR burnup calculations
    Presented at: International conference on physics of reactors (PHYSOR 2014); September 28-October 3, 2014; Kyoto, Japan.
    DORA PSI
  • Andreani M, Zboray R
    Simulation of the interaction of a horizontal jet with a stratified and condensing ambient in a large-scale, multi-compartment geometry
    Presented at: 15th international topical meeting on nuclear reactor thermal - hydraulics, NURETH-15; May 12-15, 2013; Pisa, Italy.
    DORA PSI
  • Canepa S, Hursin M, Ferroukhi H, Pautz A
    Convergence studies of deterministic methods for LWR explicit reflector methodology
    In: International conference on mathematics and computational methods applied to nuclear science and engineering (M&C 2013). Vol. 4. La Grange Park: American Nuclear Society; 2013:2868-2876. https://www.ans.org/store/item-700377/.
    DORA PSI
  • Canepa S, Hursin M, Ferroukhi H, Pautz A
    Preparation of nuclear libraries with deterministic and stochastic methods for LWR reflectors
    In: International conference on mathematics and computational methods applied to nuclear science and engineering (M&C 2013). Vol. 4. La Grange Park: American Nuclear Society; 2013:2924-2934. https://www.ans.org/store/item-700377/.
    DORA PSI
  • Hursin M, Vasiliev A, Ferroukhi H, Pautz A
    Comparison of SERPENT and CASMO-5M for pressurized water reactors models
    In: International conference on mathematics and computational methods applied to nuclear science and engineering (M&C 2013). Vol. 3. La Grange Park, IL, USA: American Nuclear Society; 2013:1565-1576. https://www.ans.org/store/item-700377/.
    DORA PSI
  • Paranjape S, Kapulla R, Mignot G, Paladino D, Zboray R
    Light water reactor hollow cone containment spray performance tests in the presence of light non-condensable gas
    Presented at: 15th international topical meeting on nuclear reactor thermal - hydraulics, NURETH-15; May 12-15, 2013; Pisa, Italy.
    DORA PSI
  • Perret G, Pattupara RM, Girardin G, Chawla R
    Reanalysis of the gas-cooled fast reactor experiments at the zero power facility Proteus – spectral indices
    In: Serot O, De Saint Jean C, Litaize O, Noguere G, eds. WONDER-2012 – 3rd international workshop on nuclear data evaluation for reactor applications. Vol. 42. EPJ web of conferences. sine loco: EDP Sciences; 2013:05002 (5 pp.). https://doi.org/10.1051/epjconf/20134205002
    DORA PSI
  • Zboray R, Mignot G, Paladino D
    Erosion and break-up of light-gas layers by horizontal injections in containment relevant atmosphere
    Presented at: 15th international topical meeting on nuclear reactor thermal - hydraulics, NURETH-15; May 12-15, 2013; Pisa, Italy.
    DORA PSI
  • Zboray R, Prasser H, Stark M
    Examining annular flows in a tight-lattice fuel bundle model by cold-neutron imaging
    Presented at: 15th international topical meeting on nuclear reactor thermal hydraulics, NURETH-15; May 12-15, 2013; Pisa, Italy.
    DORA PSI
  • Chawla R, Rätz D, Jordan KA, Perret G
    Analysis of pin removal experiments conducted in an SCWR-like test lattice
    In: PHYSOR 2012: advances in reactor physics. Vol. 4. La Grange Park, IL, USA: American Nuclear Society; 2012:3565-3578. https://www.ans.org/store/item-700371/.
    DORA PSI
  • Grimm P, Perret G
    Experimental validation of CASMO-4E and CASMO-5M for radial fission rate distributions in a westinghouse SVEA-96 Optima2 BWR fuel assembly
    In: PHYSOR 2012: advances in reactor physics. Vol. 4. La Grange Park, IL, USA: American Nuclear Society; 2012:3410-3421. https://www.ans.org/store/item-700371/.
    DORA PSI
  • Hursin M, Perret G
    Design of a PROTEUS lattice representative of a burnt and fresh fuel interface at power conditions in light water reactors
    In: PHYSOR 2012: advances in reactor physics. Vol. 5. La Grange Park: American Nuclear Society; 2012:(12 pp.).
    DORA PSI
  • Hursin M, Koeberl O, Perret G
    Towards the reanalysis of void coefficients measurements at PROTEUS for High Conversion Light Water Reactor lattices
    In: PHYSOR 2012: advances in reactor physics. Vol. 3. La Grange Park, IL, USA: American Nuclear Society; 2012:2558-2568. https://www.ans.org/store/item-700371/.
    DORA PSI
  • Kickhofel J, Fokken J, Kapulla R, Prasser HM
    Steady state RANS simulations of temperature fluctuations in single phase turbulent mixing
    In: International congress on advances in nuclear power plants 2012, ICAPP 2012. Vol. 4. ; 2012:2349-2359.
    DORA PSI
  • Mignot G, Kapulla R, Paladino D, Zboray R
    Experiment on large scale plume interaction with a stratified gas environment resembling the thermal activity of a autocatalytic recombiner
    In: Proceedings of ICAPP ‘12. ; 2012:12339 (10 pp.).
    DORA PSI
  • Paladino D, Guentay S, Andreani M, Tkatschenko I, Brinster J, Dabbene F, et al.
    The EURATOM-ROSATOM ERCOSAM-SAMARA projects on containment thermal-hydraulics of current and future LWRs for severe accident management
    In: Proceedings of ICAPP ‘12. ; 2012:1359-1368.
    DORA PSI
  • Perret G, Pattupara RM, Girardin G, Chawla R
    Reanalysis of the gas-cooled fast reactor experiments at the zero power facility proteus. Spectral indices
    In: International conference on the physics of reactors 2012. Advances in reactor physics (PHYSOR 2012). Vol. 3. ; 2012:2383-2394.
    DORA PSI
  • Perret G, Jordan KA
    On the combination of delayed neutron and delayed gamma techniques for fission rate measurement in nuclear fuel
    In: ANIMMA 2011. Proceedings. 2nd international conference on advancements in nuclear instrumentation, measurement methods and their applications. International conference on advancements in nuclear Instrumentation measurement methods and their applications (ANIMMA). Piscataway: IEEE; 2011:(7 pp.). https://doi.org/10.1109/ANIMMA.2011.6172907
    DORA PSI
  • Zboray R, Guetg M, Kickhofel J, Prasser H-M
    Investigating annular flows and the effect of functional spacers in an adiabatic double-subchannel model of a BWR fuel bundle by ultra-fast X-ray Tomography
    Presented at: 14th international topical meeting on nuclear reactor thermalhydraulics, NURETH-14; September 25-30, 2011; Toronto, Ontario, Canada.
    DORA PSI
  • Chawla R, Girardin G, Joneja OP
    Reactor experiments course of the Swiss Nuclear Engineering master
    In: Proceedings of the 18th international conference on nuclear engineering, ICONE18. Vol. 2. International conference on nuclear engineering, proceedings, ICONE. New York: American Society of Mechanical Engineers; 2010:323-330. https://doi.org/10.1115/ICONE18-29183
    DORA PSI
  • Jordan KA, Perret G, Murphy MF
    Delayed neutron measurements of induced fission rates in burnt LWR fuel samples at the proteus zero-power reactor facility
    In: International conference on the physics of reactors. American Nuclear Society; 2010:2969-2979.
    DORA PSI
  • Kröhnert H, Perret G, Murphy MF, Chawla R
    Fission rate measurements in spent fuel via gamma-ray spectrometry of short-lived fission products induced in a zero power reactor
    In: International conference on the physics of reactors 2010. Vol. 4. American Nuclear Society; 2010:2980-2991.
    DORA PSI
  • Murphy MF, Perret G, Köberl O, Jordan KA, Grimm P, Kröhnert H, et al.
    Large-scale irradiated fuel experiments at proteus research program
    In: International conference on the physics of reactors. American Nuclear Society; 2010:2747-2759.
    DORA PSI
  • Rätz D, Jordan KA, Murphy MF, Perret G, Chawla R
    Experimental validation of reaction rate distributions in an SCWR-like fuel lattice at proteus
    In: International conference on the physics of reactors. American Nuclear Society; 2010:3021-3030.
    DORA PSI
  • Kröhnert H, Murphy MF, Perret G, Chawla R
    Utilization of freshly induced high-energy gamma-ray activity as a measure of fission rates in re-irradiated burnt UO2 fuel
    In: Proceedings of the 2009 1st international conference on advancements in nuclear instrumentation, measurement methods and their applications. ANIMMA 2009 - 2009 1st international conference on advancements in nuclear instrumentation, measurement methods and their applications. Piscataway: IEEE; 2009:(6 pp.). https://doi.org/10.1109/ANIMMA.2009.5503809
    DORA PSI
  • Giust F, Grimm P, Jatuff F, Chawla R
    Comparison of reconstructed radial pin total fission rates with experimental results in full scale BWR fuel elements
    In: International conference on the physics of reactors “nuclear power: a sustainable resource”. ; 2008:(8 pp.).
    DORA PSI
  • Grimm P, Murphy MF, Jatuff F, Seiler R
    Analysis of reactivity worths of highly-burnt PWR fuel samples measured in LWR-PROTEUS Phase II
    In: Proceedings of the international conference on the physics of reactors "nuclear power: a sustainable resource". Vol. 4. International conference on the physics of reactors 2008, PHYSOR 08. Villigen: Paul Scherrer Institut; 2008:2801-2806.
    DORA PSI
  • Jaruff F, Perret G, Murphy M, Grimm P, Seiler R, Chawla R
    Impact of newly-measured gadolinium cross sections on BWR fuel rod reaction rate distributions
    In: Proceedings of the international conference on the physics of reactors "nuclear power: a sustainable resource". Vol. 1. International conference on the physics of reactors 2008, PHYSOR 08. Villigen: Paul Scherrer Institut; 2008:266-272.
    DORA PSI
  • Joneja OP, Perret G, Grimm P, Jatuff F, Chawla R
    MCNP analysis of generic configurations in the context of the LIFE@PROTEUS experiments
    In: Proceedings of the international conference on the physics of reactors "nuclear power: a sustainable resource". Vol. 1. International conference on the physics of reactors 2008, PHYSOR 08. Villigen: Paul Scherrer Institut; 2008:687-694.
    DORA PSI
  • Kröhnert H, Murphy MF, Perret G, Plaschy M, Wagemans J, Chawla R
    Measurement of fission rate ratios in fresh UO2 fuel utilising short-lived high-energy gamma activity
    In: International conference on the physics of reactors “nuclear power: a sustainable resource”. ; 2008:(8 pp.).
    DORA PSI
  • Perret G, Murphy MF, Jatuff F, Chawla R
    Fission rate distribution at the 84-pin radial section of a SVEA-96 Optima2 BWR assembly
    In: Proceedings of the international conference on the physics of reactors "nuclear power: a sustainable resource". Vol. 4. International conference on the physics of reactors 2008, PHYSOR 08. Villigen: Paul Scherrer Institut; 2008:2715-2720.
    DORA PSI
  • Caruso S, Murphy M, Jatuff F, Chawla R
    Non-invasive characterization of burnup for PWR spent fuel rods with burnups > 80 GWd/t
    In: Proceedings of ICAPP '06. Vol. 2006. Proceedings of the 2006 international congress on advances in nuclear power plants, ICAPP'06. La Grange Park: American Nuclear Society; 2006:2020-2027.
    DORA PSI
  • Lebrat JF, Plaschy M, Tommasi J, Suteau C, Plisson-Rieunier D, De Saint Jean C
    Comparative analysis of selected aspects of the muse-4 experiments with the JEF-2.2 and JEFF-3.1 libraries
    In: Vol. 2006. PHYSOR-2006 - American nuclear society's topical meeting on reactor physics. La Grange Park: American Nuclear Society; 2006:3052-3061.
    DORA PSI
  • Murphy MF, Plaschy M, Jatuff F, Bergmann U, Chawla R
    Fission and capture rate measurements in a SVEA-96 optima2 BWR assembly compared with MCNPX predictions
    In: American nuclear society's topical meeting on reactor physics. Vol. 2006. PHYSOR-2006 - American nuclear society's topical meeting on reactor physics. La Grange: American Nuclear Society; 2006:1169-1176.
    DORA PSI
  • Plaschy M, Destouches C, Chawla R, Beretz D, Mellier F, Servière H, et al.
    Determination of adjusted neutron spectra in different MUSE configurations by unfolding techniques
    In: Vehar DW, Gilliam DG, Adams JM, eds. Reactor dosimetry. 12th international symposium. Vol. 1490. West Conshohocken, PA: ASTM International; 2006:55-65. https://doi.org/10.1520/STP45426S
    DORA PSI
  • Plaschy M, Murphy M, Jatuff F, Seiler R, Chawla R
    Experimental critical loadings and control rod worths in LWR-PROTEUS configurations compared with MCNPX results
    In: PHYSOR 2006 : advances in nuclear analysis and simulation : American nuclear society's topical meeting on reactor physics. Vol. 2006. PHYSOR-2006 - American nuclear society's topical meeting on reactor physics. La Grange: American Nuclear Society; 2006:A093 (10 pp.).
    DORA PSI
  • Vollaire J, Plaschy M, Jatuff F, Chawla R
    Determination of βeffusing MCNP-4C2 and application to the CROCUS and PROTEUS reactors
    In: American nuclear society's topical meeting on reactor physics. Vol. 2006. PHYSOR-2006 - American nuclear society's topical meeting on reactor physics. La Grange: American Nuclear Society; 2006:1254-1259.
    DORA PSI

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

 

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