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

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

Please find here a selection of conferences:
 

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

2024

  • Albà A, Adelmann A, Rochman D
    Uncertainty quantification on spent nuclear fuel with LMC
    In: Suyama K, Gunji S, Watanabe T, Araki S, Fukuda K, Shimada K, et al., eds. Proceedings of the 12th international conference on nuclear criticality safety. Japan Atomic Energy Agency; 2024:1-10.
    DORA PSI
  • Berry L, Vasiliev A, Hursin M, Rochman D, Frankl M, Ferroukhi H
    Verification and validation of Monte Carlo simulations using Swiss PWR HZP data
    In: Suyama K, Gunji S, Watanabe T, Araki S, Fukuda K, Shimada K, et al., eds. Proceedings of the 12th international conference on nuclear criticality safety. Japan Atomic Energy Agency; 2024:1-10.
    DORA PSI
  • Buss O, Ferroukhi H, Ivanov K
    Updates on the OECD NEA working party on scientific issues and uncertainty analysis of reactor systems (WPRS)
    In: Proceedings of the international conference on physics of reactors (PHYSOR 2024). La Grange Park: American Nuclear Society; 2024:2268-2277. https://doi.org/10.13182/PHYSOR24-43632
    DORA PSI
  • Carmouze C, Ichou R, Ilas G, Alvarez-Velarde F, Chernykh M, García-Baonza R, et al.
    Overview of spent nuclear fuel inventory results for the ARIANE GU3 sample
    In: Suyama K, Gunji S, Watanabe T, Araki S, Fukuda K, Shimada K, et al., eds. Proceedings of the 12th international conference on nuclear criticality safety. Japan Atomic Energy Agency; 2024:1-10.
    DORA PSI
  • Cozzo C, Berti N
    Perfomance assessment of SiC cladding with cracking threshold in Falcon
    In: Proceedings of TopFuel 2024 reactor fuel performance conference. European Nuclear Society (ENS); 2024:(10 pp.).
    DORA PSI
  • D'Alessandro C, Lind T, Périllat R, Blondet G
    Preliminary strategies for training dataset generation and surrogate modelling of station blackout management measures in PWR
    In: Gabrielli F, Herranz LE, Paci S, eds. Proceedings of the 11th European review meeting on severe accidents research (ERMSAR2024). Stockholm: Karlsruher Institut für Technologie (KIT); 2024:026 (12 pp.).
    DORA PSI
  • Frankl M, Vasiliev A, Berry L, Rochman D, Ferroukhi H, Diomidis N, et al.
    Investigation of the specific keff behaviour in simplified corrosion scenarios for a potential PWR final disposal canister design
    In: Suyama K, Gunji S, Watanabe T, Araki S, Fukuda K, Shimada K, et al., eds. Proceedings of the 12th international conference on nuclear criticality safety. Japan Atomic Energy Agency; 2024:1-7.
    DORA PSI
  • Frankl M, Vasiliev A, Rochman D, Ferroukhi H, Wittel M, Pudollek S
    Refinement of the loading curve determination methodology and modeling for Swiss PWR spent fuel final disposal canisters
    In: Suyama K, Gunji S, Watanabe T, Araki S, Fukuda K, Shimada K, et al., eds. Proceedings of the 12th international conference on nuclear criticality safety. Japan Atomic Energy Agency; 2024:1-10.
    DORA PSI
  • Hoefer A, Stuke M, Abdel-Khalik HS, Cabellos O, Chernykh M, Eisenstecken T, et al.
    Bias and correlated data, comparison of methods
    In: Suyama K, Gunji S, Watanabe T, Araki S, Fukuda K, Shimada K, et al., eds. Proceedings of the 12th international conference on nuclear criticality safety. Japan Atomic Energy Agency; 2024:1-10.
    DORA PSI
  • Lind T, Bersano A, Mascari F, Herranz LE, Chaumeix N, Reinecke E, et al.
    SASPAM-SA: assessment of the relevance and applicability of existing experimental databases to iPWR
    In: Gabrielli F, Herranz LE, Paci S, eds. Proceedings of the 11th European review meeting on severe accidents research (ERMSAR2024). Stockholm: Karlsruher Institut für Technologie (KIT); 2024:057 (13 pp.).
    DORA PSI
  • Maccario S, Scolaro A, Vasiliev A, Hursin M
    Comparison of Bayesian model calibration techniques for future application to fuel performance behavior models
    In: Proceedings of the international conference on physics of reactors (PHYSOR 2024). La Grange Park: American Nuclear Society; 2024:551-560. https://doi.org/10.13182/PHYSOR24-43853
    DORA PSI
  • Martin J-F, Vasiliev A, O’Connor G, Ivanova T
    The NEA’s working party on nuclear criticality safety: tackling global challenges through international cooperation
    In: Suyama K, Gunji S, Watanabe T, Araki S, Fukuda K, Shimada K, et al., eds. Proceedings of the 12th international conference on nuclear criticality safety. Japan Atomic Energy Agency; 2024:1-10.
    DORA PSI
  • 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
  • Nikitin K, Arnold B, Clifford I, Ferroukhi H
    Critical Power Ratio (CPR) calculation methods for BWR licensing support
    In: Proceedings of SCOPE. ; 2024:23222 (8 pp.).
    DORA PSI
  • Papadionysiou M, Albagami T, Delipei G, Avramova M, Vasiliev A, Ferroukhi H, et al.
    Multi-physics sub-pin resolution analysis of a PWR core with nTRACER/CTF for the OECD/NEA TVA watts bar 1 benchmark
    In: Proceedings of the international conference on physics of reactors (PHYSOR 2024). La Grange Park: American Nuclear Society; 2024:1968-1977. https://doi.org/10.13182/PHYSOR24-43543
    DORA PSI
  • Ramos Perez A, Lind T, Petrov V, Manera A, Prasser HM
    Aerosol retention measurements with Wire-mesh sensors: an experimental and computational approach
    In: SWINTH-2024: Specialist workshop on advanced instrumentation and measurement techniques for nuclear reactor thermal hydraulics and severe accidents. Dresden: K.I.T. Group; 2024:002 (14 pp.).
    DORA PSI
  • Ramos Perez A, Lind T, Petrov V, Manera A, Prasser H-M
    Local measurements on particle mass transfer in gas-liquid flows
    In: Gabrielli F, Herranz LE, Paci S, eds. Proceedings of the 11th European review meeting on severe accidents research (ERMSAR2024). Stockholm: Karlsruher Institut für Technologie (KIT); 2024:015 (12 pp.).
    DORA PSI
  • Rochman D, Algora A, Bremnes Ø, Cabellos O, Caruso S, Fiorito L, et al.
    Decay heat of irradiated nuclear fuels – a status report from the NEA WPNCS
    In: Suyama K, Gunji S, Watanabe T, Araki S, Fukuda K, Shimada K, et al., eds. Proceedings of the 12th international conference on nuclear criticality safety. Japan Atomic Energy Agency; 2024:1-10.
    DORA PSI
  • Rochman D, Koning AJ, van der Marck SC
    The TENDL nuclear data library: for criticality calculations and more
    In: Suyama K, Gunji S, Watanabe T, Araki S, Fukuda K, Shimada K, et al., eds. Proceedings of the 12th international conference on nuclear criticality safety. Japan Atomic Energy Agency; 2024:1-8.
    DORA PSI
  • Tagliente G, Aberle O, Alcayne V, Amaducci S, Andrzejewski J, Babiano-Suarez V, et al.
    The n_TOF facility at CERN
    In: Cerutti F, Kawano T, Marin S, Pujol F, Talou P, eds. 16th Varenna conference on nuclear reaction mechanisms (NRM2023). Vol. 292. EPJ web conferences. Les Ulis Cedex A: EDP Sciences; 2024:12002 (8 pp.). https://doi.org/10.1051/epjconf/202429212002
    DORA PSI
  • Vasiliev A, Lee H, Frankl M, Hursin M, Ferroukhi H
    On the PSI routine criticality safety evaluation methodology and its validation approach
    In: Suyama K, Gunji S, Watanabe T, Araki S, Fukuda K, Shimada K, et al., eds. Proceedings of the 12th international conference on nuclear criticality safety. Japan Atomic Energy Agency; 2024:1-10.
    DORA PSI
  • Vasiliev A, Ferroukhi H, Pecchia M, Rochman D, Laureau A, Lamirand V, et al.
    Revision of PSI calculation capabilities and validation experience on the BEPU-type reactor dosimetry applications
    In: Frajtag P, Thornton D, Wagemans J, eds. ISRD 17 – International symposium on reactor dosimetry (Part II). Vol. 308. EPJ web of conferences. Les Ulis: Edp sciences; 2024:03011 (11 pp.). https://doi.org/10.1051/epjconf/202430803011
    DORA PSI
  • Vasiliev A, Frankl M, Rochman D, Wittel M, Hoefer A
    Towards a direct comparison of practical CSE with BUC approaches: benchmark for a pseudo-application case with user-defined NCS criteria
    In: Suyama K, Gunji S, Watanabe T, Araki S, Fukuda K, Shimada K, et al., eds. Proceedings of the 12th international conference on nuclear criticality safety. Japan Atomic Energy Agency; 2024:1-8.
    DORA PSI
  • Verma L, Clifford I, Ferroukhi H, Scolaro A
    Extending the validation database of Offbeat fuel performance code for Loca scenarios
    In: Proceedings of TopFuel 2024 reactor fuel performance conference. European Nuclear Society (ENS); 2024:(10 pp.).
    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

2023

  • Ahn T, Petrov V, Manera A
    Comparison between high-resolution gamma-ray tomography and wire-mesh sensor for air-water flow in a rod bundle geometry
    In: 20th international topical meeting on nuclear reactor thermal hydraulics (NURETH-20). Illinois: American Nuclear Society; 2023:2196-2209. https://doi.org/10.13182/NURETH20-40846
    DORA PSI
  • Al-Yahia OS, Bernard M, Clifford I, Perret G, Bajorek S, Ferroukhi H
    Implementation of a three-field framework in TRACE to improve the prediction of reactor core reflood conditions part II
    In: 20th international topical meeting on nuclear reactor thermal hydraulics (NURETH-20). Illinois: American Nuclear Society; 2023:110-122. https://doi.org/10.13182/NURETH20-40133
    DORA PSI
  • Alcayne V, Cano-Ott D, Garcia J, González-Romero E, Martínez T, Mendoza E, et al.
    A segmented total energy detector (sTED) for (n, γ) cross section measurements at n_TOF EAR2
    In: Mattoon CM, Vogt R, Escher J, Thompson I, eds. 15th international conference on nuclear data for science and technology (ND2022). Vol. 284. EPJ web conferences. Les Ulis Cedex A: EDP Sciences; 2023:01043 (5 pp.). https://doi.org/10.1051/epjconf/202328401043
    DORA PSI
  • Alcayne V, Mendoza E, Cano-Ott D, Kimura A, Aberle O, Amaducci S, et al.
    Results of the 244Cm, 246Cm and 248Cm neutron-induced capture cross sections measurements at EAR1 and EAR2 of the n_TOF facility
    In: Mattoon CM, Vogt R, Escher J, Thompson I, eds. 15th international conference on nuclear data for science and technology (ND2022). Vol. 284. EPJ web conferences. Les Ulis Cedex A: EDP Sciences; 2023:01009 (6 pp.). https://doi.org/10.1051/epjconf/202328401009
    DORA PSI
  • Babiano-Suarez V, Balibrea-Correa J, Caballero-Ontanaya L, Domingo-Pardo C, Ladarescu I, Lerendegui-Marco J, et al.
    High resolution 80Se(n,γ) cross section measurement at CERN n_TOF
    In: Mattoon CM, Vogt R, Escher J, Thompson I, eds. 15th international conference on nuclear data for science and technology (ND2022). Vol. 284. EPJ web conferences. Les Ulis Cedex A: EDP Sciences; 2023:01001 (6 pp.). https://doi.org/10.1051/epjconf/202328401001
    DORA PSI
  • Cabellos O, Hursin M, Palmiotti P
    WPEC/SG46 exercise on target accuracy requirement
    In: Mattoon CM, Vogt R, Escher J, Thompson I, eds. 15th international conference on nuclear data for science and technology (ND2022). Vol. 284. EPJ web conferences. Les Ulis Cedex A: EDP Sciences; 2023:14012 (4 pp.). https://doi.org/10.1051/epjconf/202328414012
    DORA PSI
  • Chae M-S, Paladino D, Kelm S
    Analyses of jet-buoyant flow in a multi-compartment containment using an open-source solver
    In: 20th international topical meeting on nuclear reactor thermal hydraulics (NURETH-20). Illinois: American Nuclear Society; 2023:4059-4072. https://doi.org/10.13182/NURETH20-40154
    DORA PSI
  • Clifford I, Kral P, Vyskocil L, Pistora V, Trewin R, Filonova Y, et al.
    State of the art for thermal-hydraulic analysis of pressurised thermal shock scenarios
    In: 20th international topical meeting on nuclear reactor thermal hydraulics (NURETH-20). Illinois: American Nuclear Society; 2023:5778-5790. https://doi.org/10.13182/NURETH20-40247
    DORA PSI
  • Clifford I, Al-Yahia OS, Ferroukhi H
    TRACE investigation on the performance of passive safety condenser as ultimate heat sink
    In: Proceedings of Saudi international conference on nuclear power engineering (SCOPE). sine loco: SCOPE; 2023:23220 (6 pp.).
    DORA PSI
  • Dehbi A, Kapulla R
    CFD simulations of large-scale tests highlighting the effects of thermal radiation in steam-containing atmospheres
    Presented at: 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
  • Domingo-Pardo C, Babiano-Suarez V, Balibrea-Correa J, Caballero L, Ladarescu I, Lerendegui-Marco J, et al.
    Compton imaging for enhanced sensitivity (n,γ) cross section TOF experiments: status and prospects
    In: Mattoon CM, Vogt R, Escher J, Thompson I, Žugec P, eds. 15th international conference on nuclear data for science and technology (ND2022). Vol. 284. EPJ web conferences. Les Ulis Cedex A: EDP Sciences; 2023:01018 (5 pp.). https://doi.org/10.1051/epjconf/202328401018
    DORA PSI
  • Domingo-Pardo C, Aberle O, Alcayne V, Altieri S, Amaducci S, Andrzejewski J, et al.
    The neutron time-of-flight facility n_TOF at CERN: recent facility upgrades and detector developments
    In: 28th international nuclear physics conference (INPC 2022). Vol. 2586. Journal of physics: conference series. Bristol: IOP Publishing; 2023:012150 (11 pp.). https://doi.org/10.1088/1742-6596/2586/1/012150
    DORA PSI
  • Dupont E, Otuka N, Rochman D, Nogèure G, Aberle O, Alcayne V, et al.
    Overview of the dissemination of n_TOF experimental data and resonance parameters
    In: Mattoon CM, Vogt R, Escher J, Thompson I, eds. 15th international conference on nuclear data for science and technology (ND2022). Vol. 284. EPJ web conferences. Les Ulis Cedex A: EDP Sciences; 2023:18001 (4 pp.). https://doi.org/10.1051/epjconf/202328418001
    DORA PSI
  • Espegren F, Suckow D, Lind T, Mantzaras J, Theile J
    Methyl iodide retention in Ag-Zeolite material under filtered containment venting system condition
    In: 20th international topical meeting on nuclear reactor thermal hydraulics (NURETH-20). Illinois: American Nuclear Society; 2023:3759-3771. https://doi.org/10.13182/NURETH20-40735
    DORA PSI
  • Faldella F, Eisenring S, Kim T, Doll U, Jansohn P
    Turbulent flame speed and flame characteristics of lean premixed H2-CH4 flames at moderate pressure levels
    In: Proceedings of ASME Turbo Expo 2023: turbomachinery technical conference and exposition. Vol. 3A. Turbo expo: power for land, sea and air. New York: American Society of Mechanical Engineers ASME; 2023:V03AT04A068 (10 pp.). https://doi.org/10.1115/gt2023-102527
    DORA PSI
  • Fogliatto E, Clifford I
    CFD simulations of the UPTF-TRAM test C1
    In: 20th international topical meeting on nuclear reactor thermal hydraulics (NURETH-20). Illinois: American Nuclear Society; 2023:606-617. https://doi.org/10.13182/NURETH20-40211
    DORA PSI
  • Freixa J, Martínez-Quiroga V, Perret G
    Assessment of the choked flow model of RELAP5 for the application of inverse quantification methods
    In: 20th international topical meeting on nuclear reactor thermal hydraulics (NURETH-20). Illinois: American Nuclear Society; 2023:5426-5439. https://doi.org/10.13182/NURETH20-40674
    DORA PSI
  • García-Infantes ME, Praena P, Casanovas P, Mastromarco M, Aberle M, Alcayne M, et al.
    First high resolution measurement of neutron capture resonances in 176Yb at the n_TOF CERN facility
    In: Mattoon CM, Vogt R, Escher J, Thompson I, eds. 15th international conference on nuclear data for science and technology (ND2022). Vol. 284. EPJ web conferences. Les Ulis Cedex A: EDP Sciences; 2023:09001 (5 pp.). https://doi.org/10.1051/epjconf/202328409001
    DORA PSI
  • Grasso M, Petrov V, Manera A, Rivera Y
    Experimental velocity profile reconstruction in thin water films
    In: 20th international topical meeting on nuclear reactor thermal hydraulics (NURETH-20). ; 2023:1516-1529. https://doi.org/10.13182/NURETH20-40771
    DORA PSI
  • Huang P-H, Ahn T, Manera A, Petrov V
    Experimental study on the start-up characteristics and performance of a ten sodium heat pipe bundle array
    In: 20th international topical meeting on nuclear reactor thermal hydraulics (NURETH-20). Illinois: American Nuclear Society; 2023:3479-3492. https://doi.org/10.13182/NURETH20-40775
    DORA PSI
  • Huxford A, Coppo Leite V, Merzari E, Zou L, Petrov V
    Validation of SAM-NekRS coupling against the TALL-3D STH/CFD coupling benchmark transient
    In: 20th international topical meeting on nuclear reactor thermal hydraulics (NURETH-20). Illinois: American Nuclear Society; 2023:518-529. https://doi.org/10.13182/NURETH20-40528
    DORA PSI
  • Ishikawa Y, Endo K, Narabayashi T, Suckow D, Espegren F, Lind T, et al.
    Advanced FCVS system using silver zeolite AgX, AgR and XeA
    In: 20th international topical meeting on nuclear reactor thermal hydraulics (NURETH-20). Illinois: American Nuclear Society; 2023:4248-4255. https://doi.org/10.13182/NURETH20-40634
    DORA PSI
  • Ishikawa Y, Endo K, Kobayashi T, Narabayashi T, Kawahara Y, Suckow DJ
    Advanced radioactive material removal system using silver zeolite (3) filtered containment venting system (FCVS) hydrogen measures
    In: Proceedings of the 2023 30th international conference on nuclear engineering ICONE30. Vol. 30. sine loco: Japan Society of Mechanical Engineers; 2023:1-3. https://doi.org/10.1299/jsmeicone.2023.30.1620
    DORA PSI
  • Kim T, Doll U, Faldella F, Jansohn P
    Quantification of mixing quality effects on flashback limits for H2-rich fuel gases
    In: Proceedings of ASME turbo expo 2023: turbomachinery technical conference and exposition (GT2023). Vol. 3A. Proceedings of the ASME turbo expo. New York: American Society of Mechanical Engineers ASME; 2023:(9 pp.). https://doi.org/10.1115/gt2023-101551
    DORA PSI
  • Lerendegui-Marco J, Casanovas A, Alcayne V, Aberle O, Altieri S, Amaducci S, et al.
    New perspectives for neutron capture measurements in the upgraded CERN-n_TOF Facility
    In: Mattoon CM, Vogt R, Escher J, Thompson I, eds. 15th international conference on nuclear data for science and technology (ND2022). Vol. 284. EPJ web conferences. Les Ulis Cedex A: EDP Sciences; 2023:01028 (6 pp.). https://doi.org/10.1051/epjconf/202328401028
    DORA PSI
  • Lind T, Kalilainen J, Marchetto C, Beck S, Nakamura K, Kino C, et al.
    OECD/NEA ARC-F project: summary of fission product transport
    In: 20th international topical meeting on nuclear reactor thermal hydraulics (NURETH-20). Illinois: American Nuclear Society; 2023:4796-4809. https://doi.org/10.13182/NURETH20-40120
    DORA PSI
  • Malicki M, Darnowski P, Lind T
    The iPWR MELCOR 2.2 parametric sensitivity analysis
    In: 20th international topical meeting on nuclear reactor thermal hydraulics (NURETH-20). Illinois: American Nuclear Society; 2023:4220-4233. https://doi.org/10.13182/NURETH20-40213
    DORA PSI
  • Manna A, Pirovano E, Colonna N, Castelluccio D, Console Camprini P, Cosentino L, et al.
    Characterization of a detector setup for the measurement of the 235U(n,f) cross section relative to n-p scattering up to 500 MeV at the n_TOF facility at CERN
    In: Mattoon CM, Vogt R, Escher J, Thompson I, eds. 15th international conference on nuclear data for science and technology (ND2022). Vol. 284. EPJ web conferences. Les Ulis Cedex A: EDP Sciences; 2023:04016 (5 pp.). https://doi.org/10.1051/epjconf/202328404016
    DORA PSI
  • Mantzaras J, Arumugan VK, Theile J, Suckow D, Espegren F, Lind T
    Recombination of hydrogen and carbon monoxide on silver-based zeolites in the presence of steam and at pressures up to 3 bar
    In: 20th international topical meeting on nuclear reactor thermal hydraulics (NURETH-20). Illinois: American Nuclear Society; 2023:4020-4033. https://doi.org/10.13182/NURETH20-40692
    DORA PSI
  • Mao J, Petrov V, Manera A
    High-resolution experiments for mixing in large enclosures
    In: 20th international topical meeting on nuclear reactor thermal hydraulics (NURETH-20). Illinois: American Nuclear Society; 2023:2152-2165. https://doi.org/10.13182/NURETH20-40559
    DORA PSI
  • Maruyama Y, Sugiyama T, Shimada A, Lind T, Bentaib A, Sogalla M, et al.
    Main outputs from the OECD/NEA ARC-F project
    In: 20th international topical meeting on nuclear reactor thermal hydraulics (NURETH-20). Illinois: American Nuclear Society; 2023:4782-4795. https://doi.org/10.13182/NURETH20-40302
    DORA PSI
  • Massimi C, Aberle O, Alcayne V, Altieri S, Amaducci S, Andrzejewski J, et al.
    Neutron-induced cross section measurements
    In: Freeman S, Lederer-Woods C, Manna A, Mengoni A, eds. Nuclear physics in astrophysics – X (NPA-X 2022). Vol. 279. EPJ web conferences. Les Ulis Cedex A: EDP Sciences; 2023:11009 (6 pp.). https://doi.org/10.1051/epjconf/202327911009
    DORA PSI
  • Mastromarco M, Manna A, García-Infantes F, Amaducci S, Mengoni A, Massimi C, et al.
    Measurement of the 160Gd(n, γ) cross section at n_TOF and its medical implications
    In: Mattoon CM, Vogt R, Escher J, Thompson I, eds. 15th international conference on nuclear data for science and technology (ND2022). Vol. 284. EPJ web conferences. Les Ulis Cedex A: EDP Sciences; 2023:09002 (5 pp.). https://doi.org/10.1051/epjconf/202328409002
    DORA PSI
  • Michalopoulou V, Diakaki M, Vlastou R, Kokkoris M, Stamatopoulos A, Tsinganis A, et al.
    Measurement of the 235U(n,f) cross section relative to the 10B(n,α) reaction with micromegas detectors at the CERN n_TOF facility: first results
    In: Mattoon CM, Vogt R, Escher J, Thompson I, eds. 15th international conference on nuclear data for science and technology (ND2022). Vol. 284. EPJ web conferences. Les Ulis Cedex A: EDP Sciences; 2023:01030 (4 pp.). https://doi.org/10.1051/epjconf/202328401030
    DORA PSI
  • Mucciola R, Paradela C, Manna A, Alaerts G, Massimi C, Kopecky S, et al.
    Neutron capture and total cross-section measurements on 94,95,96 Mo at n_TOF and GELINA
    In: Mattoon CM, Vogt R, Escher J, Thompson I, eds. 15th international conference on nuclear data for science and technology (ND2022). Vol. 284. EPJ web conferences. Les Ulis Cedex A: EDP Sciences; 2023:01031 (4 pp.). https://doi.org/10.1051/epjconf/202328401031
    DORA PSI
  • Nikitin K, Arnold B, Clifford I, Ferroukhi H
    Application of CTF subchannel code for BWR reload licensing analysis support
    In: 20th international topical meeting on nuclear reactor thermal hydraulics (NURETH-20). Illinois: American Nuclear Society; 2023:5569-5578. https://doi.org/10.13182/NURETH20-40978
    DORA PSI
  • Oprea A, Gunsing F, Schillebeeckx P, Aberle O, Bacak M, Berthoumieux E, et al.
    Measurement of the 241Am(n,γ) cross section at the n_TOF facility at CERN
    In: Mattoon CM, Vogt R, Escher J, Thompson I, eds. 15th international conference on nuclear data for science and technology (ND2022). Vol. 284. EPJ web conferences. Les Ulis Cedex A: EDP Sciences; 2023:01036 (4 pp.). https://doi.org/10.1051/epjconf/202328401036
    DORA PSI
  • Paladino D, Kapulla R, Chae MS, Paranjape S, Mignot G, Kudinov P
    PANDA experiment addressing the thermal effects in a large water pool caused by steam and a lighter non-condensable gas release from a multi-hole sparger
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    Parametric study on the modeling of the open passive containment cooling system (CWC)
    Presented at: The 13th international topical meeting on nuclear reactor thermal hydraulics, operation and safety (NUTHOS-13); September 5-10, 2022; Hsinchu.
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    Effectiveness of hydrogen recombination by AgX and AgR zeolites
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    Verification of legacy methodology of minimum critical mass estimation at PSI
    Presented at: GLOBAL 2022 - sustainable energy beyond the pandemic; July 6-8, 2022; Reims.
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    In-depth analysis for uncertain phenomena on fission product transport in the OECD/NEA ARC-F project
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    CPR estimation by CTF subchannel code with machine learning support
    Presented at: The 13th international topical meeting on nuclear reactor thermal hydraulics, operation and safety (NUTHOS-13); September5-10, 2022; Hsinchu.
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    Multifaceted coded nuclear data libraries assemblage, verification and validation: TENDL-2021
    In: International conference on radiation shielding and topical meeting of the radiation protection and shielding division. Proceedings of the 14th international conference on radiation shielding and 21st topical meeting of the radiation protection and shielding division, ICRS 2022/RPSD 2022. American Nuclear Society; 2022:308-311. https://doi.org/10.13182/ICRSRPSD22-39025
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    Millimetric fuel rod displacements: an experimental study of the impact on local thermal neutron flux in the CROCUS reactor
    In: International conference on physics of reactors. Proceedings of the international conference on physics of reactors, PHYSOR 2022. Downers Grove: American Nuclear Society; 2022:2632-2641. https://doi.org/10.13182/PHYSOR22-37846
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    Oxygen ingress measurements of a scales HTGR facility for small and medium break size DLOFC and air ingress accident scenarios
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    PIV measurements of a depressurizing jet to study helium-air mixing during HTGR depressurization accidents
     

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    Application of machine learning for online discovery of component degradation dynamics
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    Development of the methodology for degradation emulation of primary salt pump in high-temperature fluoride salt test facility
    In: Transactions of the American nuclear society. ANS winter meeting and technology expo 2022. Vol. 127. Transactions of the American Nuclear Society. American Nuclear Society; 2022:268-271. https://doi.org/10.13182/T127-39667
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    Reactivity initiated accident uncertainty quantification for fuel assembly with subchannel code
    In: International conference on physics of reactors. Proceedings of the international conference on physics of reactors, PHYSOR 2022. Downers Grove: American Nuclear Society; 2022:1667-1676. https://doi.org/10.13182/PHYSOR22-37528
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    Methodology for high-fidelity deterministic modelling of Swiss LWR fuel assemblies
    In: Margulis M, Blaise P, eds. PHYSOR2020 - international conference on physics of reactors: transition to a scalable nuclear future. Vol. 247. EPJ web of conferences. Les Ulis Cedex A: EDP Sciences; 2021:06011 (8 pp.). https://doi.org/10.1051/epjconf/202124706011
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    High resolution measurements with miniature neutron scintillators in the SUR-100 zero power reactor
    In: Lyoussi A, Carette M, Hodák R, Jenčič I, Le Dû P, Pospíšil S, et al., eds. ANIMMA 2021 - advancements in nuclear instrumentation measurement methods and their applications. Vol. 253. EPJ web of conferences. Les Ulis Cedex A: EDP Sciences; 2021:04029 (8 pp.). https://doi.org/10.1051/epjconf/202125304029
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    EUROSAFE: fostering the sharing of nuclear expertise
    In: Vázquez-Rodriguez C, Jiménez Carrascosa A, Estevez Albuja S, Duran Vinuesa LF, eds. Book of Proceedings. European nuclear young generation forum 2021. sine loco: European Nuclear Young Generation Forum; 2021:623-626.
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    Quantifying the benefits of the reduced oxidation kinetics in chromium-coated cladding: a parametric study
    In: Vázquez-Rodriguez C, Jiménez Carrascosa A, Estevez Albuja S, Duran Vinuesa LF, eds. Book of Proceedings. European nuclear young generation forum 2021. sine loco: European Nuclear Young Generation Forum; 2021:245-248.
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    Impact of various source of covariance information on integral parameters uncertainty during depletion calculations with CASMO-5
    In: Margulis M, Blaise P, eds. PHYSOR2020 - international conference on physics of reactors: transition to a scalable nuclear future. Vol. 247. EPJ web of conferences. Les Ulis Cedex A: EDP Sciences; 2021:09005 (10 pp.). https://doi.org/10.1051/epjconf/202124709005
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    Monte Carlo analysis of sub-pin resolved power behaviour in modern BWR assembly designs
    In: Proceedings of the international conference on mathematics and computational methods applied to nuclear science and engineering (M&C 2021). Illinois: American Nuclear Society (ANS); 2021:758-767. https://doi.org/10.13182/M&C21-33772
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    Non-condensable gas plugging and mixing behavior in PWR steam generator tubes during reflux condensation
    In: Proceedings of the 26th international conference on nuclear engineering (ICONE26). Thermal hydraulics and safety analyses. New York: American Society of Mechanical Engineers (ASME); 2018:ICONE26-82350 (10 pp.). https://doi.org/10.1115/ICONE26-82350
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  • Puragliesi R, Mukin R, Clifford I, Ferroukhi H, Seidl M
    Computational fluid dynamics as a tool for deriving subchannel model parameters - The PSBT case study
    In: Proceedings of the 26th international conference on nuclear engineering (ICONE26). Computational fluid dynamics (CFD); nuclear education and public acceptance. Vol. 8. New York: American Society of Mechanical Engineers (ASME); 2018:ICONE26-81743 (13 pp.). https://doi.org/10.1115/ICONE26-81743
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  • Rimpault G, Buiron L, Stauff NE, Kim TK, Taiwo TA, Lee Y-K, et al.
    Objectives and status of the OECD/NEA sub-group on Uncertainty Analysis in Modelling (UAM) for Design, Operation and Safety Analysis of SFRs (SFR-UAM)
    In: Fast reactors and related fuel cycles: next generation nuclear systems for sustainable development (FR17). Proceedings of an international conference organized by the International Atomic Energy Agency, hosted by the government of the Russian Federation through the state atomic energy corporation "Rosatom" and held in Yekaterinburg, Russian Federation, 26–29 June 2017. Vol. CN245. Proceedings series (International Atomic Energy Agency). Vienna: International Atomic Energy Agency; 2018:220 (13 pp.).
    DORA PSI
  • Rochman D, Vasiliev A, Ferroukhi H, Janin D, Seidl M
    Best estimate plus uncertainty analysis for the 244CM prediction in spent fuel characterization
    Presented at: ANS best estimate plus uncertainty international conference (BEPU 2018); May 13-18, 2018; Lucca, Italy.
    DORA PSI
  • Scolaro A, Clifford I, Fiorina C, Pautz A
    First steps towards the development of a 3D nuclear fuel behaviour solver with OpenFOAM
    In: Proceedings of the 26th international conference on nuclear engineering (ICONE26). Nuclear fuel and material, reactor physics, and transport theory. Vol. 3. sine loco: American Society of Mechanical Engineers (ASME); 2018:ICONE26-82381 (10 pp.). https://doi.org/10.1115/ICONE26-82381
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  • Siefman D, Hursin M, Aufiero M, Bidaud A, Pautz A
    Convergence analysis and criterion for data assimilation with sensitivities from Monte Carlo neutron transport codes
    In: Proceedings of the PHYSOR 2018. LaGrange Park, IL, USA: American Nuclear Society; 2018:(10 pp.).
    DORA PSI
  • Sublet J-C, Koning A, Rochman D
    TENDL-2017: the making of multi-faceted technological nuclear data library
    In: Radiation protection and shielding division 20th topical meeting. Illinois: American Nuclear Society (ANS); 2018:(7 pp.).
    DORA PSI
  • Tambouratzis T, Chionis D, Dokhane A
    General regression neural networks for the concurrent, timely and reliable identification of detector malfunctions and/or nuclear reactor deviations from steady-state operation
    In: Sundaram S, ed. Proceedings of the 2018 IEEE symposium series on computational intelligence (SSCI 2018). Piscataway: IEEE; 2018:524-531. https://doi.org/10.1109/SSCI.2018.8628700
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  • Vasiliev A, Herrero J, Rochman D, Pecchia M, Ferroukhi H, Caruso S
    Criticality safety evaluations for the concept of Swiss PWR spent fuel geological repository
    In: ANS international conference on best-estimate plus uncertainties methods (BEPU-2018). La Grange Park: American Nuclear Society; 2018:229 (12 pp.).
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  • Vasiliev A, Rochman D, Pecchia M, Ferroukhi H
    On the importance of the neutron scattering angular distributions for the LWR fast neutron dosimetry
    In: International conference on physics of reactors (PHYSOR 2018). Reactor physics paving the way towards more efficient systems. Red Hook: Curran Associates, Inc.; 2018:3686-3697.
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  • Vitullo F, Krepel J, Kalilainen J, Prasser H-M, Pautz A
    Statistical burnup distribution of moving pebbles in HTR-PM reactor
    In: Proceedings of the 26th international conference on nuclear engineering (ICONE26). Student Paper Competition. New York: American Society of Mechanical Engineers (ASME); 2018:ICONE26-81082 (10 pp.). https://doi.org/10.1115/ICONE26-81082
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  • Albiol T, Herranz L, Riera E, Dalibart C, Lind T, Del Corno A, et al.
    The European PASSAM project: R&D outcomes towards enhanced severe accident source term mitigation
    In: International congress on advances in nuclear power plants. 2017 international congress on advances in nuclear power plants, ICAPP 2017 - a new paradigm in nuclear power safety, proceedings. sine loco: International congress on advances in nuclear power plants, ICAPP; 2017:(10 pp.).
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  • Aounallah Y
    Post-dryout heat transfer assessment of trace
    In: 37th annual conference of the canadian nuclear society and 41st annual cns/cna student conference. Canadian Nuclear Society; 2017.
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  • Aounallah Y
    Simulations with TRACE of a BWR/4 steam line break under "hot standby" conditions
    In: 37th annual conference of the canadian nuclear society & 41st CNS/CNA student conference 2017. Vol. 1. Toronto, Ontario, Canada: Canadian Nuclear Society; 2017:218-228.
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  • Aounallah Y
    TRACE/S3K code coupling simulations of a BWR/4 anticipated transient without scram
    In: Proceedings of the 37th annual conference of the Canadian Nuclear Society & 41st CNS/CNA student conference 2017. Vol. 2. Toronto: Canadian Nuclear Society (CNS); 2017:1000-1013.
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  • Cabellos O, Alvarez-Velarde F, Angelone M, Diez CJ, Dyrda J, Fiorito L, et al.
    Benchmarking and validation activities within JEFF project
    In: Siegler P, Mondelaers W, Plompen A, Hambsch F-J, Schillebeeckx P, Kopecky S, et al., eds. International conference on nuclear data for science and technology. Vol. 146. EPJ Web of Conferences. EDP Sciences; 2017:06004 (6 pp.). https://doi.org/10.1051/epjconf/201714606004
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  • Chionis D, Dokhane A, Belblidia L, Pecchia M, Giardin G, Ferroukhi H, et al.
    SIMULATE-3K analyses of neutron noise response to fuel assembly vibrations and thermal-hydraulics parameters fluctuations
    In: Proceedings of the international conference on mathematics & computational methods applied to nuclear science & engineering (M&C 2017). Daejeon: Korean Nuclear Society; 2017:P289 (8 pp.).
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  • Chollet M, Cozzo C, Bertsch J, Martin M, Grolimund D, Samson V-A
    New insights in the fuel grain subdivision during in-plant irradiation up to high burn-up
    Presented at: Water reactor fuel performance meeting 2017 (WRFPM 2017); September 10-14, 2017; Jeju, Korea.
    DORA PSI
  • Coindreau O, Jäckel B, Rocchi F, Alcaro F, Angelova D, Bandini G, et al.
    Severe accident code-to-code comparison for two accident scenarios in a spent fuel pool
    Presented at: 8th European review meeting on severe accident research (ERMSAR 2017); May 16-18, 2017; Warsaw, Poland.
    DORA PSI
  • Cozzo C, Bertsch J, Fave L, Rahman S, Dokhane A, Krack M, et al.
    SiC cladding behavior: experiments and modelling at PSI
    Presented at: Water reactor fuel performance meeting 2017 (WRFPM 2017); September 10-14, 2017; Jeju, Korea.
    DORA PSI
  • Curti E, Krack M, Grolimund D, Churakov SV
    The chemical state of 79Se in spent nuclear fuel: Implications for the performance assessment
    In: 16th international high-level radioactive waste management conference. Creating a safe and secure energy future for generations to come - driving toward long-term storage and disposal. American Nuclear Society; 2017:281-285.
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  • Dehbi A, Kelm S, Kalilainen J, Mueller H
    The influence of thermal radiation on the free convection inside enclosures
    Presented at: 8th European review meeting on severe accident research (ERMSAR 2017); May 16-18, 2017; Warsaw, Poland.
    DORA PSI
  • Dokhane A, Grandi G, Leray O, Rochman D, Vasiliev A, Ferroukhi H
    Nuclear data uncertainty decomposition for SPERT-III RIA experiments using SIMULATE-3K and SHARK-X
    In: Proceedings of the international conference on mathematics & computational methods applied to nuclear science & engineering (M&C 2017). Daejeon: Korean Nuclear Society; 2017:P236 (8 pp.).
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  • Fischer U, Avrigeanu M, Avrigeanu V, Cabellos O, Dzysiuk N, Koning A, et al.
    Nuclear data for fusion technology - the European approach
    In: Siegler P, Mondelaers W, Plompen A, Hambsch F-J, Schillebeeckx P, Kopecky S, et al., eds. International conference on nuclear data for science and technology. Vol. 146. EPJ Web of Conferences. EDP Sciences; 2017:09003 (6 pp.). https://doi.org/10.1051/epjconf/201714609003
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  • Fischer U, Angelone M, Avrigeanu M, Avrigeanu V, Bachmann C, Dzysiuk N, et al.
    The role of nuclear data for fusion nuclear technology
    Presented at: International symposium on fusion nuclear technology; September 25-29, 2017; Kyoto, Japan.
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  • Fleming M, Sublet J-C, Gilbert MR, Koning A, Rochman D
    TALYS/TENDL verification and validation processes: Outcomes and recommendations
    In: Plompen A, Hambsch F-J, Schillebeeckx P, Mondelaers W, Heyse J, Kopecky S, et al., eds. ND 2016: international conference on nuclear data for science and technology. Vol. 146. EPJ web of conferences. sine loco: EDP Sciences; 2017:02033 (4 pp.). https://doi.org/10.1051/epjconf/201714602033
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  • García-Herranz N, Panadero A-L, Martinez A, Pelloni S, Mikityuk K, Pautz A
    Nuclear data sensitivity and uncertainty assessment of sodium voiding reactivity coefficients of an ASTRID-like sodium fast reactor
    In: Plompen A, Hambsch F-J, Schillebeeckx P, Mondelaers W, Heyse J, Kopecky S, et al., eds. ND 2016: international conference on nuclear data for science and technology. Vol. 146. EPJ web of conferences. sine loco: EDP Sciences; 2017:09006 (6 pp.). https://doi.org/10.1051/epjconf/201714609006
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  • Griffin P, Rochman D, Koning A
    Characterization of the energy-dependent uncertainty and correlation in silicon neutron displacement damage metrics
    In: Plompen A, Hambsch F-J, Schillebeeckx P, Mondelaers W, Heyse J, Kopecky S, et al., eds. ND 2016: international conference on nuclear data for science and technology. Vol. 146. EPJ web of conferences. sine loco: EDP Sciences; 2017:02008 (6 pp.). https://doi.org/10.1051/epjconf/201714602008
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  • Herrero JJ, Rochman D, Leray O, Vasiliev A, Pecchia M, Ferroukhi H, et al.
    Impact of nuclear data uncertainty on safety calculations for spent nuclear fuel geological disposal
    In: Plompen A, Hambsch F-J, Schillebeeckx P, Mondelaers W, Heyse J, Kopecky S, et al., eds. ND 2016: international conference on nuclear data for science and technology. Vol. 146. EPJ web of conferences. sine loco: EDP Sciences; 2017:09028 (4 pp.). https://doi.org/10.1051/epjconf/201714609028
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  • 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
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  • Jaeckel B, Steiner P, Klügel J-U
    Progression of postulated loss-of-cooling accidents in the wet storage pool of NPP Gösgen/Däniken
    In: Proceedings of NENE 2017. Ljubljana: Nuclear Society of Slovenia; 2017:402.1 (8 pp.).
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  • Leray O, Rochman D, Fleming M, Sublet J-C, Koning A, Vasiliev A, et al.
    Fission yield covariances for JEFF: a Bayesian Monte Carlo method
    In: Plompen A, Hambsch F-J, Schillebeeckx P, Mondelaers W, Heyse J, Kopecky S, et al., eds. ND 2016: international conference on nuclear data for science and technology. Vol. 146. EPJ web of conferences. sine loco: EDP Sciences; 2017:09023 (4 pp.). https://doi.org/10.1051/epjconf/201714609023
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  • Mala P, Pautz A, Canepa S, Ferroukhi H
    Nodal and pin-by-pin calculations comparison with codes SIMULATE-5 and DYN3D
    In: International conference on mathematics & computational methods applied to nuclear science & engineering (M&C 2017). Daejeon: Korean Nuclear Society; 2017:(9 pp.).
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  • 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.
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  • Mukin R, Clifford I, Ferroukhi H, Seidl M
    Thermal hydraulic analysis of PWR assembly bowing using subchannel code COBRA-TF
    Presented at: 17th international topical meeting on nuclear reactor thermal hydraulics (NURETH 2017); September 3-8, 2017; Xi'an, China.
    DORA PSI
  • Mukin R, Puragliesi R, Ceuca SC, Austregesilo H, Bousbia Salah A
    Thermal mixing assessment using 3-D thermal-hydraulic and CFD codes
    Presented at: 17th international topical meeting on nuclear reactor thermal hydraulics (NURETH 2017); September 3-8, 2017; Xi'an, China.
    DORA PSI
  • Palmiotti G, Salvatores M, Hursin M, Kodeli I, Gabrielli F, Hummel A
    New approaches to provide feedback from nuclear and covariance data adjustment for effective improvement of evaluated nuclear data files
    In: Plompen A, Hambsch F-J, Schillebeeckx P, Mondelaers W, Kopecky S, Siegler P, et al., eds. ND 2016: international conference on nuclear data for science and technology. Vol. 146. EPJ web of conferences. sine loco: EDP Sciences; 2017:06003 (11 pp.). https://doi.org/10.1051/epjconf/201714606003
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  • Pettersen EE, Mikityuk K
    Simulating circulating-fuel fast reactors with the coupled TRACE-PARCS code
    In: Fast reactors and related fuel cycles: next generation nuclear systems for sustainable development (FR17). Proceedings of an international conference organized by the International Atomic Energy Agency, hosted by the government of the Russian Federation through the state atomic energy corporation "Rosatom" and held in Yekaterinburg, Russian Federation, 26–29 June 2017. Vol. CN245. Proceedings series (International Atomic Energy Agency). Vienna: International Atomic Energy Agency; 2017:059 (10 pp.).
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  • Rochman D, Mala P, Ferroukhi H, Vasiliev A, Seidl M, Janin D, et al.
    Bowing effects on power and burn-up distributions for simplified full PWR and BWR cores
    In: Proceedings of the international conference on mathematics & computational methods applied to nuclear science & engineering (M&C 2017). Daejeon: Korean Nuclear Society; 2017:P286 (7 pp.).
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  • Rochman D, Koning AJ, Sublet JC, Fleming M, Bauge E, Hilaire S, et al.
    The TENDL library: hope, reality and future
    In: Plompen A, Hambsch F-J, Schillebeeckx P, Mondelaers W, Heyse J, Kopecky S, et al., eds. ND 2016: international conference on nuclear data for science and technology. Vol. 146. EPJ web of conferences. sine loco: EDP Sciences; 2017:02006 (5 pp.). https://doi.org/10.1051/epjconf/201714602006
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  • Rýdl A, Lind T, Fernandez-Moguel L
    Modeling of fission roduct scrubbing in experiments and in integral severe accident scenarios
    Presented at: 8th European review meeting on severe accident research (ERMSAR 2017); May 16-18, 2017; Warsaw, Poland.
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  • Siefman DJ, Hursin M, Grimm P, Pautz A
    Case study of data assimilation methods with the LWR-Proteus Phase II experimental campaign
    In: Proceedings of the international conference on mathematics & computational methods applied to nuclear science & engineering (M&C 2017). Daejeon: Korean Nuclear Society; 2017:(10 pp.).
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  • Sjöstrand H, Conroy S, Helgesson P, Hernandez SA, Koning A, Pomp S, et al.
    Propagation of nuclear data uncertainties for fusion power measurements
    In: Plompen A, Hambsch F-J, Schillebeeckx P, Mondelaers W, Heyse J, Kopecky S, et al., eds. ND 2016: international conference on nuclear data for science and technology. Vol. 146. EPJ web of conferences. sine loco: EDP Sciences; 2017:02034 (4 pp.). https://doi.org/10.1051/epjconf/201714602034
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  • Szogradi M, Janasz F, Ki-Yong C
    Reflux condensation with various non-condensable gases
    In: Proceedings of the 3nd world congress on mechanical, chemical, and material engineering (MCM'17). Orléans, ON, Canada: Avestia, International ASET Inc.; 2017:168 (8 pp.). https://doi.org/10.11159/htff17.168
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  • Albiol T, Herranz L, Riera E, Dalibart C, Lind T, Del Corno A, et al.
    Preliminary insights from the PASSAM project: investigation on enhancement of source term mitigation
    In: Proceedings of the 11th international topical meeting on nuclear reactor thermal hydraulics, operation and safety (NUTHOS-11). La Grange Park: American Nuclear Society; 2016:N11P0580 (14 pp.).
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    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.).
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  • Aounallah Y
    Simulations of level-swell experiments with TRACE
    Presented at: 11th international topical meeting on nuclear reactor thermal hydraulics, operation and safety (NUTHOS-11); October 9-13, 2016; Gyeongju, Korea.
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  • Bocharov D, Krack M, Kalinko A, Purans J, Rocca F, Ali SE, et al.
    Ab initio molecular dynamics simulations of the Sc K-edge EXAFS of scandium trifluoride
    In: Grunwaldt J-D, Hagelstein M, Rothe J, eds. 16th international conference on X-ray absorption fine structure (XAFS16). Vol. 712. Journal of physics: conference series. Bristol, Philadelphia: IOP Publishing; 2016:012009 (4 pp.). https://doi.org/10.1088/1742-6596/712/1/012009
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  • Bocharov D, Chollet M, Krack M, Bertsch J, Grolimund D, Martin M, et al.
    Interpretation of the U L3-edge EXAFS in uranium dioxide using molecular dynamics and density functional theory simulations
    In: 16th international conference on X-ray absorption fine structure (XAFS16). Vol. 712. Journal of physics: conference series. Bristol, Philadelphia: IOP Publishing; 2016:12091 (4 pp.). https://doi.org/10.1088/1742-6596/712/1/012091
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  • Bykov V, Vasiliev A, Ferroukhi H, Pautz A
    Solution of the BEAVRS benchmark using CASMO-5 / SIMULATE-5 code sequence
    In: Physics of reactors 2016 (PHYSOR 2016). Unifying theory and experiments in the 21st century. LaGrange Park, IL, USA: American Nuclear Society; 2016:1960-1968.
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  • Canepa S, Ferroukhi H, Min R, Joo HG
    Comparative study of CASMO-5/simulate-5 and nTRACER for EPR core analyses
    In: International congress on advances in nuclear power plants, ICAPP 2016. Vol. 2. American Nuclear Society; 2016:1436-1445.
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  • Chionis D, Dokhane A, Ferroukhi H, Pautz A
    On causality analysis of nuclear reactor noise using partial directed coherence
    In: Physics of reactors 2016 (PHYSOR 2016). Unifying theory and experiments in the 21st century. LaGrange Park, IL, USA: American Nuclear Society; 2016:1162-1171.
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  • Clifford I, Zerkak O, Pautz A, Yao H, Freixa J
    System code validation series based on a consistent plant nodalisation of the ROSA/LSTF integral test facility using TRACE v5.0 Patch 4
    Presented at: 11th international topical meeting on nuclear reactor thermal hydraulics, operation and safety (NUTHOS-11); October 9-13, 2016; Gyeongju, Korea.
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  • Cozzo C, Epiney A, Canepa S, Ferroukhi H, Zerkak O, Khvostov G, et al.
    Full core LOCA analysis for BWR/6 - methodology and first results
    In: Top Fuel 2016. LWR fuels with enhanced safety and performance. LaGrange Park, IL, USA: American Nuclear Society; 2016:1135-1144.
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  • Degueldre C, Fiorina C
    The proto-Earth geo-reactor: a thorium reactor?
    In: Revol J-P, Bourquin M, Kadi Y, Lillestol E, de Mestral J-C, Samec K, eds. Thorium energy for the world. Proceedings of the ThEC13 conference, CERN, globe of science and innovation, Geneva, Switzerland, October 27-31, 2013. Cham: Springer; 2016:415-416. https://doi.org/10.1007/978-3-319-26542-1
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  • Dehbi A, Han F, Kalilainen J
    Large Eddy Simulations of flow inside a cubical differentially heated cavity under realistic boundary conditions
    In: Computational fluid dynamics for nuclear reactor safety-5 (CFD4NRS-5). Workshop proceedings. Paris: OECD; 2016:(13 pp.).
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  • Dehbi A, Kalilainen J
    Large Eddy Simulations of free convection particle transport inside cavities at Rayleigh numbers up to 1010
    In: Computational fluid dynamics for nuclear reactor safety applications-6 (CFD4NRS-6). Workshop proceedings. Paris: OECD; NEA; 2016:(16 pp.).
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  • Dokhane A, Leray O, Rochman D, Ferroukhi H, Pautz A, Grandi G
    Validation of SIMULATE-3K against SPERT-III RIA experiments with quantification of nuclear data uncertainties
    In: Physics of reactors 2016 (PHYSOR 2016). Unifying theory and experiments in the 21st century. LaGrange Park, IL, USA: American Nuclear Society; 2016:3803-3812.
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  • Fei T, Vezzoni B, Marchetti M, van Rooijen WFG, Zhang Y
    Neutronics benchmark for EBR-II shutdown heat removal test SHRT-45R
    In: Physics of reactors 2016 (PHYSOR 2016). Unifying theory and experiments in the 21st century. LaGrange Park, IL, USA: American Nuclear Society; 2016:221-230.
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  • 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.
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  • Halouane Y, Dehbi A
    Comparison of hydrogen flame acceleration predictions using the Eddy-Dissipation and the Turbulent Flame Closure
    In: Computational fluid dynamics for nuclear reactor safety applications-6 (CFD4NRS-6). Workshop proceedings. Paris: OECD; NEA; 2016:(15 pp.).
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  • 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.
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  • Jacquemain D, Albiol T, Dickinson S, Herranz L-E, Funke F, Glowa G, et al.
    Conclusion of the international OECD/NEA-NUGENIA iodine workshop
    In: Proceedings of the 11th international topical meeting on nuclear reactor thermal hydraulics, operation and safety (NUTHOS-11). La Grange Park: American Nuclear Society; 2016:N11PA0625 (20 pp.).
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  • Kalilainen J, Prasser H-M, Lind T, Krepel J, Schenler W
    Recent research activities on high temperature pebble bed reactors at PSI
    In: 2016 international topical meeting on high temperature reactor technology (HTR 2016). Illinois: American Nuclear Society; 2016:135-140.
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  • Krepel J, Hombourger B, Bykov V, Fiorina C, Mikityuk K, Pautz A
    Paul Scherrer Institute's studies on advanced molten salt reactor fuel cycle options
    In: Revol J-P, Bourquin M, Kadi Y, Lillestol E, de Mestral J-C, Samec K, eds. Thorium energy for the world. Proceedings of the ThEC13 conference, CERN, globe of science and innovation, Geneva, Switzerland, October 27-31, 2013. Cham: Springer; 2016:185-192. https://doi.org/10.1007/978-3-319-26542-1_29
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  • Krepel J, Mikityuk K, Pautz A
    The EQL0D procedure for fuel cycle studies in molten salt reactor
    In: 2016 International Congress on Advances in Nuclear Power Plants, ICAPP 2016. ; 2016.
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  • 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.
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  • Leray O, Fiorito L, Rochman D, Ferroukhi H, Pautz A, Stankovskiy A, et al.
    Comparison of fission yield perturbation methodologies on nuclide composition for a PWR UO2 fuel assembly
    In: Physics of reactors 2016 (PHYSOR 2016). Unifying theory and experiments in the 21st century. LaGrange Park, IL, USA: American Nuclear Society; 2016:1669-1680.
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  • Li J, Rochman D, Herrero J, Ferrouki H, Vasiliev A, Pautz A
    Towards analysis of the bowing effect on burnt nuclear fuel compositions using SERPENT
    Presented at: American Nuclear Society 2016 student conference; March 31 - April 3, 2016; University of Wisconsin, Madison, USA.
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  • Lind T, Beghi I, Opilik L, Suckow D
    The effect of thermal-hydraulic conditions on iodine retention in a wet scrubber of the FCVS
    In: Proceedings of the 11th international topical meeting on nuclear reactor thermal hydraulics, operation and safety (NUTHOS-11). La Grange Park: American Nuclear Society; 2016:N11P1234 (12 pp.).
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  • Mignot G, Dupont J, Paladino D, Prasser H-M
    Containment thermal-hydraulic experiment and potential for severe accident studies in the LINX facility
    Presented at: 11th international topical meeting on nuclear reactor thermal hydraulics, operation and safety (NUTHOS-11); October 9-13, 2016; Gyeongju, Korea.
    DORA PSI
  • Mikityuk K
    Fast reactor physics
    In: Revol J-P, Bourquin M, Kadi Y, Lillestol E, de Mestral J-C, Samec K, eds. Thorium energy for the world. Proceedings of the ThEC13 conference, CERN, globe of science and innovation, Geneva, Switzerland, October 27-31, 2013. Cham: Springer; 2016:215-221. https://doi.org/10.1007/978-3-319-26542-1_33
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  • Mukin R, Zerkak O, Pautz A
    Modeling and analysis of selected OECD PKL3 Station-Blackout experiments using TRACE
    Presented at: 11th international topical meeting on nuclear reactor thermal hydraulics, operation and safety (NUTHOS-11); October 9-13, 2016; Gyeongju, Korea.
    DORA PSI
  • Mukin R, Dehbi A
    Simulation of flow on the secondary side of a steam generator bundle
    In: Computational fluid dynamics for nuclear reactor safety-5. (CFD4NRS-5). Workshop proceedings. Paris, France: OECD; 2016. https://www.oecd-nea.org/nsd/csni/cfd/.
    DORA PSI
  • Paranjape S, Kapulla R, Mignot G, Paladino D
    Erosion of a helium layer due to the flow resulting from the interaction of a steam jet with a flow obstruction in a large vessel
    Presented at: 11th international topical meeting on nuclear reactor thermal hydraulics, operation and safety (NUTHOS-11); October 9-13, 2016; Gyeongju, Korea.
    DORA PSI
  • Pelloni S
    A progressive incremental adjustment methodology for cross-section and variance/covariance data adjustment for fast-spectrum systems
    Presented at: PHYSOR 2016: unifying theory and experiments in the 21st century; May 1-5, 2016; Sun Valley, ID, USA.
    DORA PSI
  • Perret G
    Delayed neutron fraction and prompt decay constant measurement in the Minerve reactor using the PSI instrumentation
    In: 2015 4th international conference on advancements in nuclear instrumentation measurement methods and their applications (ANIMMA). 2015 4th international conference on advancements in nuclear instrumentation measurement methods and their applications (ANIMMA). Danvers: IEEE; 2016:8 pp. https://doi.org/10.1109/ANIMMA.2015.7465533
    DORA PSI
  • Perret G, Vlassopoulos E, Hursin M, Pautz A
    Toward reanalysis of the tight-pitch HCLWR-PROTEUS Phase II experiments
    In: Serot O, ed. Wonder-2015 – 4th international workshop on nuclear data evaluation for reactor applications. Vol. 111. EPJ web of conferences. Les Ulis Cedex A, France: EDP Sciences; 2016:11006 (9 pp.). https://doi.org/10.1051/epjconf/201611111006
    DORA PSI
  • Puragliesi R, Zerkak O, Pautz A
    Influence of URANS turbulence models on in-vessel flow mixing during cold leg accumulator injection
    Presented at: 11th international topical meeting on nuclear reactor thermal hydraulics, operation and safety (NUTHOS-11); October 9-13, 2016; Gyeongju, Korea.
    DORA PSI
  • Rahman S, Karanki DR, Wicaksono D, Zerkak O, Dang VN
    Evaluation of deterministic sampling for uncertainty quantification in a probabilistic accident analysis model
    Presented at: 11th international topical meeting on nuclear reactor thermal hydraulics, operation and safety (NUTHOS-11); October 9-13, 2016; Gyeongju, Korea.
    DORA PSI
  • Rais A, Hursin M, Perret G, Pautz A
    Experimental validation of control rod reactivity worth and fission rate distributions for the CROCUS Reactor
    In: Physics of reactors 2016 (PHYSOR 2016). Unifying theory and experiments in the 21st century. Vol. 6. LaGrange Park, IL, USA: American Nuclear Society; 2016:3874-3883.
    DORA PSI
  • Rýdl A, Fernandez-Moguel L, Lind T
    Impact of containment venting on source term for Fukushima-like BWR scenarios
    Presented at: 11th international topical meeting on nuclear reactor thermal hydraulics, operation and safety (NUTHOS-11); October 9-13, 2016; Gyeongju, Korea.
    DORA PSI
  • Savelli R, Vasiliev A, Ferroukhi H, Pautz A
    Extention of PSI FNF modeling methodology validation using BWR dosimetry data
    Presented at: American Nuclear Society 2016 student conference; March 31 - April 3, 2016; University of Wisconsin, Madison, USA.
    DORA PSI
  • Sublet JC, Koning AJ, Rochman D, Fleming M, Gilbert M
    TENDL-2015: Delivering both completeness and robustness
    In: Advances in nuclear nonproliferation technology and policy conference (ANTPC 2016). Advances in nuclear nonproliferation technology and policy conference: bridging the gaps in nuclear nonproliferation, ANTPC 2016. American Nuclear Society; 2016:(4 pp.).
    DORA PSI
  • Wicaksono D, Zerkak O, Pautz A
    Bayesian calibration of thermal-hydraulics model with time-dependent output
    Presented at: 11th international topical meeting on nuclear reactor thermal hydraulics, operation and safety (NUTHOS-11); October 9-13, 2016; Gyeongju, Korea.
    DORA PSI

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

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

 

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

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

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

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

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

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

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

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

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

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

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

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

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

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

 

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  • 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
  • Aufiero M, Fiorina C, Laureau A, Rubiolo P, Valtavirta V
    Serpent-OpenFOAM coupling in transient mode: simulation of a Godiva prompt critical burst
    In: Mathematics and computations, supercomputing in nuclear applications and Monte Carlo international conference (M&C and SNA and MC 2015). Mathematics and computations, supercomputing in nuclear applications and Monte Carlo international conference (M&C+SNA+MC 2015). LaGrange Park, IL, USA: American Nuclear Society; 2015:1995-2006.
    DORA PSI
  • Bortot S, Alvarez-Velarde F, Fridman E, Garcia Cruzado I, Garcia Herranz N, López D, et al.
    European benchmark on the ASTRID-like low-void-effect core characterization: neutronic parameters and safety coefficients
    In: Proceedings of 2015 international congress on advances in nuclear power plants (ICAPP 2015). Paris, France: SFEN; 2015:668-676. https://www.sfen.org/.
    DORA PSI
  • Brankov V, Khvostov G, Mikityuk K, Pautz A, Restani R, Abolhassani S, et al.
    Modeling of axial distribution of released fission gas in KKL BWR fuel rods during base irradiation
    In: TopFuel 2015. Reactor fuel performance. Conference proceedings. Part 1. Brussels: European Nuclear Society; 2015:609-619.
    DORA PSI
  • Briggs L, Hu W, Su GH, Vezzoni B, Del Nevo A, Monti S, et al.
    EBR-II passive safety demonstration tests benchmark analyses-phase 2
    In: 16th International Topical meeting on nuclear reactor thermal hydraulics, NURETH 2015. Vol. 4. American Nuclear Society; 2015:3030-3043.
    DORA PSI
  • Bubelis E, Schikorr M, Frogheri M, Mansani L, Bandini G, Burgazzi L, et al.
    LFR safety approach and main ELFR safety analysis results
    In: Track 3 - safety. Vienna: International Atomic Energy Agency; 2015:IAEA-CN-199/297 (10 pp.).
    DORA PSI
  • Bykov V, Volmert B, Pautz A
    Enhancement and Validation of BWR MCNP Activation Simulations for Swiss Decommissioning Planning
    Presented at: 2015 American Nuclear Society Student Conference; April 9-11, 2015; College Station, TX, USA.
    DORA PSI
  • Canepa S, Krack M, Ferroukhi H, Pautz A
    Scalability benchmarking methodology for hybrid parallel core calculations with the code nTRACER
    In: Mathematics and computations, supercomputing in nuclear applications and Monte Carlo international conference (M&C and SNA and MC 2015). LaGrange Park, IL, USA: American Nuclear Society; 2015:2819-2831.
    DORA PSI
  • Chionis D, Hofer K, Pautz A
    Peak cladding temperature prediction and assessment for the Leibstadt NPP using SIMULATE-3K
    In: 2015 ANS student conference. Powering tomorrow together. La Grange Park: American Nuclear Society; 2015:(6 pp.).
    DORA PSI
  • Chollet M, Krsjak V, Cozzo C, Bertsch J
    Positron annihilation spectroscopy study of lattice defects in non-irradiated doped and un-doped fuels
    In: TopFuel 2015. Reactor fuel performance. Conference proceedings. Part 1. Brussels: European Nuclear Society; 2015:502-509.
    DORA PSI
  • Chollet M, Krack M, Kuzmin A, Bertsch J, Grolimund D, Martin M
    Theoretical modelling of pristine and chromium-doped UO2
    Presented at: E-MRS 2015; May 11-15, 2015; Lille, France.
    DORA PSI
  • Clifford I, Vasiliev A, Zerkak O, Ferroukhi H, Pautz A
    Computational fluid dynamics analysis of the fluid flow and heat transfer in the core bypass region of a PWR
    In: 16th international topical meeting on nuclear reactor thermal hydraulics (NURETH-16). LaGrange Park, IL, USA: American Nuclear Society; 2015:7806-7819.
    DORA PSI
  • Dehbi A
    A generalized correlation for steam condensation rates in the presence of air-helium mixtures
    In: 16th international topical meeting on nuclear reactor thermal hydraulics (NURETH 2016). Vol. 10. American Nuclear Society; 2015:8347-8359.
    DORA PSI
  • Dokhane A, Zerkak O, Ferroukhi H, Gajev I, Judd J, Kozlowski T
    TRACE/SIMULATE-3K analysis of the NEA/OECD Oskarshamn-2 stability benchmark
    In: 16th international topical meeting on nuclear reactor thermal hydraulics (NURETH-16). LaGrange Park, IL, USA: American Nuclear Society; 2015:4757-4770.
    DORA PSI
  • Epiney A, Canepa S, Zerkak O, Ferroukhi H
    Towards a consolidated approach for the validation of plant system codes and models: case study for a BWR fast depressurisation event
    In: 16th international topical meeting on nuclear reactor thermal hydraulics (NURETH-16). LaGrange Park, IL, USA: American Nuclear Society; 2015:2157-2170.
    DORA PSI
  • Fernandez-Moguel L, Rydl A, Jaeckel B
    Analysis of Fukushima Daiichi NPP unit 3 with Melcor_2.1
    In: 16th international topical meeting on nuclear reactor thermal hydraulics (NURETH-16). LaGrange Park, IL, USA: American Nuclear Society; 2015:6401-6411.
    DORA PSI
  • Fiorina C, Mikityuk K
    Application of the new GeN-Foam multi-physics solver to the European Sodium Fast Reactor and verification against available codes
    In: Proceedings of 2015 international congress on advances in nuclear power plants (ICAPP 2015). Paris, France: SFEN; 2015:2017-2024. https://www.sfen.org/.
    DORA PSI
  • Fiorina C, Mikityuk K, Pautz A
    GeN-Foam: a novel multi-physics solver for reactor analysis - status and ongoing developments
    In: Federici G, Corradini ML, Klein AC, Uckan NA, Rimpault G, Cacuci DG, et al., eds. Proceedings of the American Nuclear Society. Vol. 113. Transactions of the American Nuclear Society. La Grange Park: American Nuclear Society; 2015:1132-1134. https://www.ans.org/pubs/transactions/article-38067/.
    DORA PSI
  • Ghasabyan L, Mikityuk K, Krepel J, Pelloni S
    Use of Serpent Monte-Carlo code for development of 3D full-core models of Gen-IV fast spectrum reactors and preparation of safety parameters/cross-section data for transient analysis
    In: Track 7 - experiments and simulation. Vienna: International Atomic Energy Agency; 2015:(10 pp.).
    DORA PSI
  • Grasso G, Döderlein C, Tučekc K, Mikityuk K, Manni F, Gugiu D
    A core design approach aimed at the sustainability and intrinsic safety of the European Lead-cooled Fast Reactor
    In: Track 1 - designs. Vienna: International Atomic Energy Agency; 2015:97-106.
    DORA PSI
  • Grasso G, Petrovic C, Mikityuk K, Mattioli D, Manni F, Gugiu D
    Demonstrating the effectiveness of the European LFR concept: the ALFRED core design
    In: Track 1 - designs. Vienna: International Atomic Energy Agency; 2015:IAEA-CN-199/312 (10 pp.).
    DORA PSI
  • Herrero JJ, Pecchia M, Ferroukhi H, Canepa S, Vasiliev A, Caruso S
    Computational scheme for burnup credit applied to long term waste disposal
    In: ICNC 2015 - international conference on nuclear criticality safety. LaGrange Park, IL, USA: American Nuclear Society; 2015:1783-1791.
    DORA PSI
  • Hombourger B, Pautz A, Krepel J, Mikityuk K
    Fuel cycle analysis of a Molten Salt Reactor for Breed-and-Burn mode
    In: Proceedings of 2015 international congress on advances in nuclear power plants (ICAPP 2015). Paris, France: SFEN; 2015:910-916.
    DORA PSI
  • Hursin M, Joo HG, Downar TJ
    Assessment of thermal hydraulic feedbacks effects during modeling of a RIA using direct whole core transport solution
    In: Mathematics and computations, supercomputing in nuclear applications and Monte Carlo international conference (M&C and SNA and MC 2015). LaGrange Park, IL, USA: American Nuclear Society; 2015:2394-2405.
    DORA PSI
  • Hursin M, Rossinelli L, Ferroukhi H, Pautz A
    BWR full core analysis with SERPENT/SIMULATE-3 hybrid stochastic/determinstic code sequence
    In: Mathematics and computations, supercomputing in nuclear applications and Monte Carlo international conference (M&C and SNA and MC 2015). LaGrange Park, IL, USA: American Nuclear Society; 2015:1794-1806.
    DORA PSI
  • Kapulla R, Kelm S, Mignot G, Paranjape S, Paladino D
    Experimental and numerical results for the erosion dynamics of a vertical helium-air jet interacting with a helium rich layer
    In: Proceedings of ICAPP 2015. Vol. 49. INIS. Paris: SFEN; 2015:15242 (16 pp.). https://inis.iaea.org/search/search.aspx?num=10&orig_q=RN%3a49005001&lang=en-US&login=false&user=External&src=&sort=date:D:L:d1&sortorder=ascending&search-option=Everywhere&q=+inmeta:ConferenceTitle%3DICAPP%25202015%253A%2520Nuclear%2520Innovations%2.
    DORA PSI
  • 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
  • Krepel J, Fiorina C, Mikityuk K
    Comparison of several recycling strategies and relevant fuel cycles for molten salt reactor
    In: Proceedings of 2015 international congress on advances in nuclear power plants (ICAPP 2015). Paris, France: SFEN; 2015.
    DORA PSI
  • Krepel J, Pelloni S, Bortot S, Panadero AL, Mikityuk K
    Mapping of sodium void worth and Doppler effect for sodium-cooled fast reactor
    In: Proceedings of 2015 international congress on advances in nuclear power plants (ICAPP 2015). Paris, France: SFEN; 2015:677-684. https://www.sfen.org/.
    DORA PSI
  • Krepel J, Brankov V, Mikityuk K
    Selection of initial fuel composition for the ESFR core based on the knowledge of its equilibrium closed cycle parameters
    In: Track 8 - deployment and scenarios. Vienna: International Atomic Energy Agency; 2015:(9 pp.).
    DORA PSI
  • Kriventsev V, Rineiski A, Pfrang W, Perez-Martin S, Mikityuk K, Khvostov G
    Benchmark on behavior of MOX fuel pin under irradiation at nominal power in sodium fast reactor
    In: TopFuel 2015. Reactor fuel performance. Conference proceedings. Part 2. Brussels: European Nuclear Society; 2015:550-559.
    DORA PSI
  • Leray O, Pecchia M, Vasiliev A, Ferroukhi H, Pautz A, Perrier H
    Development, verification and test application of a hybrid CASMO-5/SERPENT depletion scheme
    In: Mathematics and computations, supercomputing in nuclear applications and Monte Carlo international conference (M&C and SNA and MC 2015). LaGrange Park, IL, USA: American Nuclear Society; 2015:1781-1793.
    DORA PSI
  • Mala P, Canepa S, Ferroukhi H, Pautz A
    Preparation of pin-by-pin nuclear libraries with superhomogenization method for nTRACER and DORT core calculations
    In: Mathematics and computations, supercomputing in nuclear applications and Monte Carlo international conference (M&C and SNA and MC 2015). LaGrange Park, IL, USA: American Nuclear Society; 2015:775-786.
    DORA PSI
  • Mignot G, Paranjape S, Kapulla R, Paladino D
    Performance of hydrogen mitigation systems for a scaled accident scenario: overview of ERCOSAM project experimental results for the PANDA facility
    In: 16th international topical meeting on nuclear reactor thermal hydraulics (NURETH-16). LaGrange Park, IL, USA: American Nuclear Society; 2015:5456-5469.
    DORA PSI
  • Mikityuk K, Schikorr M
    New transient analysis of the Superphenix start-up tests
    In: Track 9 - decommissioning. Vienna: International Atomic Energy Agency; 2015:IAEA-CN-199/297155 (10 pp.).
    DORA PSI
  • Mikityuk K, Perkó Z, Girardin G
    Reactivity effect of steam/water ingress in Generation-IV Gas-cooled Fast Reactor core
    In: Track 3 - safety. Vienna: International Atomic Energy Agency; 2015:(7 pp.).
    DORA PSI
  • 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
  • Park S, Fernandez-Moguel L, Prasser H-M, Birchley J, Steinbrück M, Seifert H-J
    Effect of nitriding during an air ingress scenario
    In: TopFuel 2015. Reactor fuel performance. Conference proceedings. Part 2. Brussels: European Nuclear Society; 2015:380-390.
    DORA PSI
  • Pecchia M, Herrero JJ, Ferroukhi H, Vasiliev A, Canepa S, Pautz A
    COMPLINK: a versatile tool for automatizing the representation of material data in MCNP models
    In: ICNC 2015 - international conference on nuclear criticality safety. LaGrange Park, IL, USA: American Nuclear Society; 2015:513-522.
    DORA PSI
  • Pelloni S, Aufiero M, Bortot S, Krepel J, Mikityuk K, Panadero AL, et al.
    Sodium void map preparation for the safety analysis of Sodium-cooled Fast Reactors by using the Monte Carlo code Serpent
    In: Proceedings of 2015 international congress on advances in nuclear power plants (ICAPP 2015). Paris, France: SFEN; 2015. https://www.sfen.org/.
    DORA PSI
  • Poette C, Guedeney P, Stainsby R, Mikityuk K, Knol S
    Gas cooled fast reactors: recent advances and prospects
    In: Track 1 - designs. Vienna: International Atomic Energy Agency; 2015:(10 pp.).
    DORA PSI
  • Puragliesi R, Zerkak O, Pautz A, Zhou Q
    Assessment of OpenFOAM CFD toolbox for gravity driven mixing flows in a Reactor Pressure Vessel
    In: 16th international topical meeting on nuclear reactor thermal hydraulics (NURETH-16). LaGrange Park, IL, USA: American Nuclear Society; 2015:952-965.
    DORA PSI
  • Rahman S, Karanki DR, Epiney A, Zerkak O, Dang VN
    Ranking of uncertain parameters for dynamic event tree analysis: a case study based on a Station Black Out scenario
    In: 16th international topical meeting on nuclear reactor thermal hydraulics (NURETH-16). LaGrange Park, IL, USA: American Nuclear Society; 2015:5734-5747.
    DORA PSI
  • Rineiski A, Vezzoni B, Zhang D, Marchetti M, Gabrielli F, Maschek W, et al.
    ESFR core optimization and uncertainty studies
    In: Track 1 - designs. Vienna: International Atomic Energy Agency; 2015:265-274.
    DORA PSI
  • Rýd A, Jäckel B, Klügel J-U, Steiner P
    Melt-concrete interface heat transfer models and coolability models: PWR analyses with MELCOR/CORCON and CORQUENCH
    In: 16th international topical meeting on nuclear reactor thermal hydraulics (NURETH-16). LaGrange Park, IL, USA: American Nuclear Society; 2015:484-498.
    DORA PSI
  • Vasile A, Wahide C, Latge C, Chauvin N, Baeten P, Schyns M, et al.
    The European project ESNII Plus
    In: Proceedings of 2015 international congress on advances in nuclear power plants (ICAPP 2015). Paris, France: SFEN; 2015:928-936. https://www.sfen.org/.
    DORA PSI
  • Vasiliev A, Rochman D, Zhu T, Pecchia M, Ferroukhi H, Pautz A
    Towards application of neutron cross-section uncertainty propagation capability in the criticality safety methodology
    In: ICNC 2015 - international conference on nuclear criticality safety. LaGrange Park, IL, USA: American Nuclear Society; 2015:606-615.
    DORA PSI
  • Vrban B, Čerba Š, Lüley J, Haščík J, Nečas V, Pelloni S
    Investigation of the coupled reactivity effects of the movable reflector and safety control rods in the GFR
    In: Track 3 - safety. Vienna: International Atomic Energy Agency; 2015:144 (11 pp.).
    DORA PSI
  • Wicaksono D, Zerkak O, Pautz A
    A methodology for global sensitivity analysis of transient code output applied to a reflood experiment model using TRACE
    In: 16th international topical meeting on nuclear reactor thermal hydraulics (NURETH-16). LaGrange Park, IL, USA: American Nuclear Society; 2015:4862-4879.
    DORA PSI
  • Zanetti M, Cammi A, Luzzi L, Křepel J, Mikityuk K
    Extension of the FAST code system for the modelling and simulation of MSR dynamics
    In: Proceedings of ICAPP 2015. Paris, France: SFEN; 2015:883-890.
    DORA PSI
  • Zboray R, Dangendorf V, Mor I, Tittelmeier K, Bromberger B, Prasser H-M
    Time-resolved fast neutron radiography of air-water two-phase flows
    In: Lehmann EH, Kaestner AP, Mannes D, eds. Proceedings of the 10th world conference on neutron radiography (WCNR-10) Grindelwald, Switzerland October 5-10, 2014. Vol. 69. Physics procedia. sine loco: Elsevier; 2015:551-555. https://doi.org/10.1016/j.phpro.2015.07.078
    DORA PSI
  • Zhang Y, Mikityuk K
    Validation of the Serpent and TRACE codes using the SHRT-17 and SHRT-45R loss-of-flow tests performed in the EBR-II reactor
    In: Proceedings of 2015 international congress on advances in nuclear power plants (ICAPP 2015). Paris, France: SFEN; 2015:495-503. https://www.sfen.org/.
    DORA PSI

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

  • Aounallah Y
    Assessment of TRACE against single-tube post-dryout heat transfer experiments
    Presented at: 10th international topical meeting on nuclear thermal-hydraulics, operation and safety (NUTHOS-10); December 14-18, 2014; Okinawa, Japan.
    DORA PSI
  • Betschart T, Suckow D, Brankov V, Prasser HM
    The hydrodynamics of two-phase flow in a tube bundle and a bare channel
    In: Vol. 2. International congress on advances in nuclear power plants (ICAPP 2014). American Nuclear Society; 2014:1403-1411.
    DORA PSI
  • Bortot S, Pelloni S, Mikityuk K
    Methodology assessment for the evaluation of the coolant void worth in Sodium Fast Reactors with a low void effect core design
    Presented at: International conference on physics of reactors (PHYSOR 2014); September 28-October 3, 2014; Kyoto, Japan.
    DORA PSI
  • Buhagiar K, Lerch P, Gabard A, Buzio M, Sanfilippo S, Foussat A
    Magnetic survey of large magnets: a 1 to 5 scale model system
    In: IMEKO TC4 symposium on measurements of electrical quantities. IMEKO-International Measurement Federation Secretariat; 2014:904-909.
    DORA PSI
  • Bykov V, Křepel J, Pautz A
    Molten salt fast reactor blanket design and proliferation resistance assessment
    In: Proceedings of the 2014 22nd international conference on nuclear engineering (ICONE22). New York: American Society of Mechanical Engineers (ASME); 2014:V005T17A061 (9 pp.). https://doi.org/10.1115/ICONE22-31026
    DORA PSI
  • Clifford I, Zerkak O, Pautz A
    Post-test analysis of OECD/NEA ROSA-2 test 4 using TRACE
    Presented at: 10th international topical meeting on nuclear thermal-hydraulics, operation and safety (NUTHOS-10); December 14-18, 2014; Okinawa, Japan.
    DORA PSI
  • Deshpande SS, Niceno B, Mutz A, Klügel J
    Multiphase and turbulence models' sensitivity study in pressurized thermal shock simulations of the TOPFLOW experiment
    In: International congress on advances in nuclear power plants (ICAPP 2014). Vol. 2. American Nuclear Society; 2014:1426-1435.
    DORA PSI
  • Dokhane A, Ferroukhi H, Pautz A
    Analysis of the OECD/NEA Oskarshamn-2 feedwater transient and stability benchmark with simulate-3K
    In: Proceedings of the international conference on physics of reactors (PHYSOR 2014). PHYSOR 2014 – the role of reactor physics toward a sustainable future. ; 2014:1101708 (14 pp.).
    DORA PSI
  • Dupont J, Mignot G, Zboray R, Prasser H-MP
    Characterization and validation of the near infrared film thickness profile technique
    Presented at: 10th international topical meeting on nuclear thermal-hydraulics, operation and safety (NUTHOS-10); December 14-18, 2014; Okinawa, Japan.
    DORA PSI
  • Dupré A, Vasiliev A, Ferroukhi H, Pautz A
    Validation enhancements of the PSI Fast Neutron Fluence computational scheme using operational PWR experimental data
    Presented at: American Nuclear Society 2014 student conference; April 3-6, 2014; Pennsylvania.
    DORA PSI
  • Epiney A, Zerkak O, Pautz A
    Uncertainty- and sensitivity analysis of COBRA-TF for the simulation of selected OECD/NRC BFBT void experiments
    Presented at: 10th international topical meeting on nuclear thermal-hydraulics, operation and safety (NUTHOS-10); December 14-18, 2014; Okinawa, Japan.
    DORA PSI
  • Fiorina C, Mikityuk K, Křepel J
    A procedure for the pre-conceptual design of fast reactors and application to a gas-cooled sub-critical transmuter
    In: Proceedings of the 2014 22nd international conference on nuclear engineering (ICONE22). New York: American Society of Mechanical Engineers (ASME); 2014:V005T16A001 (9 pp.). https://doi.org/10.1115/ICONE22-30387
    DORA PSI
  • Fiorina C, Aufiero M, Pelloni S, Mikityuk K
    A time-dependent solver for coupled neutron-transport thermal-mechanics calculations and simulation of a Godiva prompt-critical burst
    In: Proceedings of the 2014 22nd international conference on nuclear engineering (ICONE22). New York: American Society of Mechanical Engineers (ASME); 2014:V004T11A008 (9 pp.). https://doi.org/10.1115/ICONE22-30395
    DORA PSI
  • Fiorina C, Cammi A, Luzzi L, Mikityuk K, Ninokata H, Ricotti ME
    Thermal-hydraulics of internally heated molten salts and application to the Molten Salt Fast Reactor
    In: 31st UIT (Italian union of thermo-fluid-dynamics) heat transfer conference 2013. Vol. 501. Journal of physics: conference series. Bristol, UK: IOP Publishing; 2014:012030 (10 pp.). https://doi.org/10.1088/1742-6596/501/1/012030
    DORA PSI
  • Geuss M, Panzer HKF, Clifford ID, Lohmann B
    Parametric model order reduction using pseudoinverses for the matrix interpolation of differently sized reduced models
    In: Boje E, Xia X, eds. World congress on international federation of automatic control. Vol. 19. IFAC Proceedings Volumes (IFAC-PapersOnline). IFAC; 2014:9468-9473. https://doi.org/10.3182/20140824-6-za-1003.02404
    DORA PSI
  • Grimm P, Perret G, Ferroukhi H
    CASMO-4E AND CASMO-5 analysis of the isotopic compositions of the LWR-PROTEUS phase II burnt PWR UO2 fuel samples
    Presented at: International conference on physics of reactors (PHYSOR 2014); September 28-October 3, 2014; Kyoto, Japan.
    DORA PSI
  • Herranz LE, Tardáguila RD, Berschart T, Lind T, Morandi S
    Remaining issues in pool scrubbing: major drivers for experimentation within the EU-PASSAM project
    In: Proceedings of ICAPP '14. Vol. 2. International congress on advances in nuclear power plants, ICAPP 2014. La Grange Park: American Nuclear Society; 2014:14156 (9 pp.).
    DORA PSI
  • Hombourger BA, Křepel J, Mikityuk K, Pautz A
    Parametric lattice study of a graphite-moderated molten salt reactor
    In: Proceedings of the 2014 22nd international conference on nuclear engineering (ICONE22). New York: American Society of Mechanical Engineers (ASME); 2014:V005T17A063 (7 pp.). https://doi.org/10.1115/ICONE22-31050
    DORA PSI
  • Hursin M, Ferroukhi H, Pautz A
    Neutronic Data Generation for BWR Models, Comparison OF SERPENT and CASMO-5
    Presented at: ANS student conference 2014; April 3-6, 2014; University Park, PA, USA.
    DORA PSI
  • Hursin M, Scriven M, Perret G, Grimm P, Pautz A
    Pinpower uncertainty quantification of LWR-PROTEUS phase III experiments
    Presented at: International conference on physics of reactors (PHYSOR 2014); September 28-October 3, 2014; Kyoto, Japan.
    DORA PSI
  • Hursin M, Siefman D, Rais A, Girardin G, Pautz A
    Verification of a reactor physics calculation scheme for the CROCUS reactor
    In: 3rd international technical meeting on small reactors. Vol. 1. Toronto, Canada: Canadian nuclear society; 2014. https://infoscience.epfl.ch/record/253153/files/ITSMR_2014.pdf.
    DORA PSI
  • Jaeckel B, Birchley J, Fernandez-Moguel L
    Spent fuel pool under severe accident conditions
    In: Proceedings of the 2014 22nd international conference on nuclear engineering (ICONE22). New York: American Society of Mechanical Engineers (ASME); 2014:V003T06A029 (7 pp.). https://doi.org/10.1115/ICONE22-30729
    DORA PSI
  • Kapulla R, Mignot G, Paranjape S, Paladino D
    Stably stratified helium layer erosion by a vertical buoyant helium-air jet
    In: Proceedings of the 2014 international congress on advances in nuclear power plants. La Grange Park: American Nuclear Society; 2014:(23 pp.). https://www.ans.org/store/item-700385/.
    DORA PSI
  • Karanki DR, Zerkak O, Dang VN
    Treatment of epistemic and aleatory uncertainties in DET simulations: computational framework with ADS-TRACE
    Presented at: 10th international topical meeting on nuclear thermal-hydraulics, operation and safety (NUTHOS-10); December 14-18, 2014; Okinawa, Japan.
    DORA PSI
  • Křepel J, Mikityuk K, Hombourger B, Pautz A, Zanetti M, Aufiero M, et al.
    Hybrid spectrum Molten Salt Reactor
    Presented at: International conference on physics of reactors (PHYSOR 2014); September 28-October 3, 2014; Kyoto, Japan.
    DORA PSI
  • Křepel J, Bykov V, Mikityuk K, Hombourger B, Fiorina C, Pautz A
    Molten salt reactor with simplified fuel recycling and delayed carrier salt cleaning
    In: Proceedings of the 2014 22nd international conference on nuclear engineering (ICONE22). New York: American Society of Mechanical Engineers (ASME); 2014:V003T05A015 (11 pp.). https://doi.org/10.1115/ICONE22-30396
    DORA PSI
  • Leray O, Grimm P, Ferroukhi H, Pautz A
    Quantification of code, library and cross-section uncertainty effects on the void reactivity coefficient of a BWR UO2 assembly
    Presented at: International conference on physics of reactors (PHYSOR 2014); September 28-October 3, 2014; Kyoto, Japan.
    DORA PSI
  • Leray O, Pecchia M, Vasiliev A, Ferroukhi H, Pautz A
    Reactivity benchmark Analysis and Code Reactivity Prediction for a PWR Fuel Assembly
    Presented at: ANS student conference 2014; April 3-6, 2014; University Park, PA, USA.
    DORA PSI
  • Leray O, Grimm P, Hursin M, Ferroukhi H, Pautz A
    Uncertainty quantification of spent fuel nuclide compositions due to cross sections, decay constants and fission yields
    Presented at: International conference on physics of reactors (PHYSOR 2014); September 28-October 3, 2014; Kyoto, Japan.
    DORA PSI
  • Mala P, Canepa S, Ferroukhi H, Pautz A
    Effects of advanced radial submeshing methods on pin power reconstruction for an EPR core design
    Presented at: International conference on physics of reactors (PHYSOR 2014); September 28-October 3, 2014; Kyoto, Japan.
    DORA PSI
  • Mukin R, Dehbi A
    Simulation of a gas jet in the secondary side of a steam generator bundle following a tube rupture sequence
    In: Proceedings of the 2014 22nd international conference on nuclear engineering (ICONE22). New York: American Society of Mechanical Engineers (ASME); 2014:V004T10A018 (9 pp.). https://doi.org/10.1115/ICONE22-30517
    DORA PSI
  • Ngayam-Happy RA, Krack M
    Radiation damage characterization in non-stoichiometric uranium dioxide by molecular dynamics simulations
    In: Caruge D, Calvin C, Diop CM, Malvagi F, Trama J-C, eds. SNA and MC 2013 - joint international conference on supercomputing in nuclear applications and monte carlo. sine loco: EDP Sciences; 2014:01301 (2 pp.). https://doi.org/10.1051/snamc/201401301
    DORA PSI
  • Paladino D, Mignot G, Kapulla R, Paranjape S, Andreani M, Studer E, et al.
    OECD/NEA HYMERES project: for the analysis and mitigation of a severe accident leading to hydrogen release into a nuclear plant containment
    In: International congress on advances in nuclear power plants (ICAPP 2014). Vol. 2. Illinois: American Nuclear Society (ANS); 2014:1314-1322.
    DORA PSI
  • Paranjape S, Mignot G, Paladino D
    Effect of thermal stratification on full cone spray performance in reactor containment for a scaled scenario
    In: Proceedings of the 2014 22nd international conference on nuclear engineering (ICONE22). New York: American Society of Mechanical Engineers (ASME); 2014:V02BT09A020 (14 pp.). https://doi.org/10.1115/ICONE22-30755
    DORA PSI
  • Pascal V, Prulhiere G, Vanier M, Fontaine B, Devan K, Chellapandi P, et al.
    IAEA benchmark calculations on control rod withdrawal test performed during PHENIX End-Of-Life Experiments – benchmark results and comparisons
    Presented at: International conference on physics of reactors (PHYSOR 2014); September 28-October 3, 2014; Kyoto, Japan.
    DORA PSI
  • Pecchia M, Vasiliev A, Ferroukhi H, Pautz A
    Updated validation of the PSI criticality safety evaluation methodology using MCNPX2.7 and ENDF/B-VII.1
    Presented at: International conference on physics of reactors (PHYSOR 2014); September 28-October 3, 2014; Kyoto, Japan.
    DORA PSI
  • Puragliesi R, Zerkak O, Pautz A
    Assessment of CFD uRANS models for buoyancy driven mixing flows based on ROCOM experiments
    Presented at: 10th international topical meeting on nuclear thermal-hydraulics, operation and safety (NUTHOS-10); December 14-18, 2014; Okinawa, Japan.
    DORA PSI
  • Rais A, Siefman D, Girardin G, Hursin M, Pautz A
    PARCS few-group homogenized parameters generation using Serpent Monte Carlo code at the CROCUS reactor
    In: 16h meeting of the international group on research reactors. sine loco: IGORR; 2014:(11 pp.). https://www.igorr.com/Documents/2014-BARILOCHE/AdolfoRAIS-CROCUS.pdf.
    DORA PSI
  • Rydl A, Jaeckel B, Birchley JC, Lind T
    Long-term SBO with selected mitigative measures: MELCOR parametric calculations for a 2-loop PWR
    In: Proceedings of the 2014 22nd international conference on nuclear engineering (ICONE22). New York: American Society of Mechanical Engineers (ASME); 2014:V006T15A012 (10 pp.). https://doi.org/10.1115/ICONE22-30351
    DORA PSI
  • Vasiliev A, Wieselquist W, Ferroukhi H, Canepa S, Heldt J, Ledergerber G
    Validation studies of computational scheme for high-fidelity fluence estimations of the Swiss BWRs
    In: Vol. 4. Progress in nuclear science and technology. Tokyo: Atomic Energy Society of Japan; 2014:99-103. https://doi.org/10.15669/pnst.4.99
    DORA PSI
  • Wicaksono D, Zerkak O, Pautz A
    Exploring variability in reflood simulation results: an application of functional data analysis
    Presented at: 10th international topical meeting on nuclear thermal-hydraulics, operation and safety (NUTHOS-10); December 14-18, 2014; Okinawa, Japan.
    DORA PSI
  • Wicaksono D, Zerkak O, Pautz A
    Sensitivity analysis of a bottom reflood simulation using the Morris screening method
    Presented at: 10th international topical meeting on nuclear thermal-hydraulics, operation and safety (NUTHOS-10); December 14-18, 2014; Okinawa, Japan.
    DORA PSI
  • Wicaksono D, Grimm P, Vasiliev A, Hursin M, Perret G, Ferroukhi H
    Validation of two Monte Carlo codes for LWR burnup calculations
    Presented at: International conference on physics of reactors (PHYSOR 2014); September 28-October 3, 2014; Kyoto, Japan.
    DORA PSI
  • Yang J, Suckow D, Prasser H-M, Michel F, Lind T
    Assessment of RELAP5/TRACE against VEFITA thermal-hydraulic level swell tests
    In: Proceedings of ICAPP 2014. Vol. 3. International congress on advances in nuclear power plants, ICAPP 2014. La Grange Park: American Nuclear Society; 2014:14154 (8 pp.).
    DORA PSI
  • Yun Y, Leray O, Ferroukhi H
    Uncertainty and sensitivity analysis of OECD/NEA UAM fuel thermal behaviour benchmark using a Falcon/URANIE methodology
    Presented at: International conference on physics of reactors (PHYSOR 2014); September 28-October 3, 2014; Kyoto, Japan.
    DORA PSI
  • Zanetti M, Luzzi L, Cammi A, Fiorina C
    An innovative approach to dynamics modeling and simulation of the Molten Salt Rector Experiment
    Presented at: International conference on physics of reactors (PHYSOR 2014); September 28-October 3, 2014; Kyoto, Japan.
    DORA PSI
  • Andreani M, Zboray R
    Simulation of the interaction of a horizontal jet with a stratified and condensing ambient in a large-scale, multi-compartment geometry
    Presented at: 15th international topical meeting on nuclear reactor thermal - hydraulics, NURETH-15; May 12-15, 2013; Pisa, Italy.
    DORA PSI
  • Bortot S, Wallenius J, Suvdantsetseg E, Pelloni S
    Modeling issues in small HLMC fast reactors: ELECTRA case study
    In: Vol. 109. Transactions of the American nuclear society. American Nuclear Society; 2013:2261-2264.
    DORA PSI
  • Bubelis E, Schikorr M, Mansani L, Bandini G, Mikityuk K, Zhang Y, et al.
    Safety analysis results of the DBC transients performed for the ALFRED reactor
    In: Track 3 - safety. Vienna: International Atomic Energy Agency; 2013:IAEA-CN-199/298 (10 pp.).
    DORA PSI
  • Canepa S, Hursin M, Ferroukhi H, Pautz A
    Convergence studies of deterministic methods for LWR explicit reflector methodology
    In: International conference on mathematics and computational methods applied to nuclear science and engineering (M&C 2013). Vol. 4. La Grange Park: American Nuclear Society; 2013:2868-2876. https://www.ans.org/store/item-700377/.
    DORA PSI
  • Canepa S, Hursin M, Ferroukhi H, Pautz A
    Preparation of nuclear libraries with deterministic and stochastic methods for LWR reflectors
    In: International conference on mathematics and computational methods applied to nuclear science and engineering (M&C 2013). Vol. 4. La Grange Park: American Nuclear Society; 2013:2924-2934. https://www.ans.org/store/item-700377/.
    DORA PSI
  • Degueldre C, Cozzo C, Martin M, Grolimund D, Poonoosamy J, Kulik D
    Redox behaviour of americium in mixed oxide fuels
    In: Vol. 2. LWR fuel performance meeting, Top Fuel 2013. American Nuclear Society; 2013:1195-1200.
    DORA PSI
  • Dehbi A, Lind T, Suckow D, Guentay S
    PSI steam generator project: mixing and recirculation
    In: Proceedings of ICAPP 2013. International congress on advances in nuclear power plants, ICAPP 2013: nuclear power - a safe and sustainable choice for green future, held with the 28th KAIF/KNS annual conference. Daejeon: Korean Nuclear Society; 2013:FA123 (8 pp.).
    DORA PSI
  • Dokhane A, Ferroukhi H, Pautz A
    On BWR regional oscillations with rotational symmetry line using SIMULATE-3K
    In: International conference on mathematics and computational methods applied to nuclear science and engineering, M and C 2013. ; 2013:1773-1785.
    DORA PSI
  • Fiorina C, Cammi A, Ricotti ME, Krepel J, Mikityuk K
    Analysis of void reactivity and Doppler coefficient for thorium- and uranium-fuelled lead fast reactors
    In: Proceedings of ICAPP 2013. Daejeon: Korean Nuclear Society; 2013:FD127 (10 pp.).
    DORA PSI
  • Fiorina C, Krepel J
    MSFR TRU-burining potential and comparison with an SFR
    Presented at: GLOBAL 2013: International Nuclear Fuel Cycle Conference; September 29 - October 3, 2013; Salt Lake City, USA.
    DORA PSI
  • Fiorina C, Franceschini F, Cammi A, Krepel J
    MSFR TRU-burning potential and comparison with an SFR
    In: Vol. 1. International nuclear fuel cycle conference, GLOBAL 2013: nuclear energy at a crossroads. American Nuclear Society; 2013:813-822.
    DORA PSI
  • Fiorina C, Franceschini F, Cammi A, Krepel J
    The MSFR as a flexible CR reactor: the viewpoint of safety
    In: Proceedings of GLOBAL 2013: international nuclear fuel cycle conference - nuclear energy at a crossroads. Vol. 2. La Grange Park, IL, USA: American Nuclear Society; 2013:833-842.
    DORA PSI
  • Freixa J, Belaid S, Zerkak O
    Thermal-hydraulic system code performance for SBLOCA phenomonelogy using different geometries and scales
    Presented at: 15th international topical meeting on nuclear reactor thermal-hydraulics, NURETH-15; May 12-17, 2013; Pisa.
    DORA PSI
  • Hursin M, Vasiliev A, Ferroukhi H, Pautz A
    Comparison of SERPENT and CASMO-5M for pressurized water reactors models
    In: International conference on mathematics and computational methods applied to nuclear science and engineering (M&C 2013). Vol. 3. La Grange Park, IL, USA: American Nuclear Society; 2013:1565-1576. https://www.ans.org/store/item-700377/.
    DORA PSI
  • Ihalainen M, Lind T, Torvela T, Ruusunen J, Lähde A, Tiitta P, et al.
    Fragmentation and bounce of nanosized agglomerates due to the impaction
    In: Particle technology forum 2013. AIChE; 2013:129-130.
    DORA PSI
  • Khvostov G, Pautz A, Kolstad E, Ledergerber G
    Analysis of a Halden LOCA test with the BWR high burnup fuel
    In: LWR fuel performance meeting. TopFuel 2013. LaGrange Park, IL, USA: American Nuclear Society (ANS); 2013:644-651.
    DORA PSI
  • Krepel J, Fiorina C, Kliem S
    Advantages and dynamics features of liquid fueled MSR
    In: Proceedings of the conference on molten salts in nuclear technology. sine loco: sine nomine; 2013:16-25.
    DORA PSI
  • Krepel J, Hombourger B, Mikityuk K
    Dependence of the thorium closed fuel cycle parameters on the moderation level of the molten salt reactor
    In: Proceedings of ICAPP 2013. Daejeon, South Korea: Korean Nuclear Society; 2013:483-492.
    DORA PSI
  • Lind T, Güntay S, Dehbi A, Suckow D
    The results of the ARTIST project - consequence analysis of a spontaneous SGTR
    In: Proceedings of ICAPP 2013. International congress on advances in nuclear power plants, ICAPP 2013: nuclear power - a safe and sustainable choice for green future, held with the 28th KAIF/KNS annual conference. Korean Nuclear Society; 2013:FA121 (10 pp.).
    DORA PSI
  • Nikitin K, Gudmundsson T, Canepa S, Zerkak O, Ferroukhi H, Pautz A
    Post-analysis of a turbine trip test at a BWR/6 using the TRACE/S3K coupled code
    Presented at: 15th international topical meeting on nuclear reactor thermal-hydraulics, NURETH-15; May 12-17, 2013; Pisa.
    DORA PSI
  • Papini D, Zerkak O, Prasser H
    Simulation of international standard problem ISP-42 phase B using in-house coupled code GOTHIC-TRACE
    Presented at: 15th international topical meeting on nuclear reactor thermal hydraulics, NURETH-15; May 12-15, 2013; Pisa, Italy.
    DORA PSI
  • Paranjape S, Kapulla R, Mignot G, Paladino D, Zboray R
    Light water reactor hollow cone containment spray performance tests in the presence of light non-condensable gas
    Presented at: 15th international topical meeting on nuclear reactor thermal - hydraulics, NURETH-15; May 12-15, 2013; Pisa, Italy.
    DORA PSI
  • Pascal V, Prulhière G, Fontaine B, Devan K, Chellapandi P, Kriventsev V, et al.
    Benchmark calculations on control rod withdrawal tests performed during PHENIX end-of-life experiments
    In: Proceedings of ICAPP 2013. Daejeon: Korean Nuclear Society; 2013:408-418.
    DORA PSI
  • Perret G, Pattupara RM, Girardin G, Chawla R
    Reanalysis of the gas-cooled fast reactor experiments at the zero power facility Proteus – spectral indices
    In: Serot O, De Saint Jean C, Litaize O, Noguere G, eds. WONDER-2012 – 3rd international workshop on nuclear data evaluation for reactor applications. Vol. 42. EPJ web of conferences. sine loco: EDP Sciences; 2013:05002 (5 pp.). https://doi.org/10.1051/epjconf/20134205002
    DORA PSI
  • Polidori M, Meloni P, Mikityuk K, Bubelis E, Schikorr M, Geffraye G, et al.
    Thermal-hydraulic codes benchmark for gas-cooled fast reactor systems based on HEFUS3 experimental data
    In: International congress on advances in nuclear power plants. Korean Nuclear Society; 2013:908-917.
    DORA PSI
  • Wallenius J, Bortot S, Suvdantsetseg E
    Electra-forte, A really small SMR for the Canadian market
    In: Vol. 109. Transactions of the American nuclear society. American Nuclear Society; 2013:2258-2260.
    DORA PSI
  • Wicaksono D, Zerkak O, Nikitin K, Ferroukhi H, Chawla R
    Application of power time-projection on the operator-splitting coupling scheme of the trace/S3K coupled code
    In: International conference on mathematics and computational methods applied to nuclear science and engineering (M&C 2013). Vol. 3. La Grange Park, IL, USA: American Nuclear Society; 2013:1748-1760. https://www.ans.org/store/item-700377/.
    DORA PSI
  • Yang J
    Parameter study of RELAP5 LOCA simulation on initial and boundary conditions
    In: Vol. 108. Transactions of the American nuclear society. American Nuclear Society; 2013:980-983.
    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
  • Chawla R
    Reactor physics teaching and research in the Swiss nuclear engineering master
    In: International conference on the physics of reactors 2012. Advances in reactor physics (PHYSOR 2012). Vol. 2. ; 2012:1502-1511.
    DORA PSI
  • Chenu A, Mikityuk K, Chawla R
    Analysis of phenix natural convection test with the TRACE code
    In: International congress on advances in nuclear power plants 2012, ICAPP 2012. Vol. 3. ; 2012:1810-1818.
    DORA PSI
  • Dehbi A, Badreddine H
    CFD study of natural convection mixing in a steam generator mock-up: comparison between full geometry and porous media approaches
    In: International congress on advances in nuclear power plants 2012, ICAPP 2012. Vol. 4. ; 2012:2231-2238.
    DORA PSI
  • Dokhane A, Canepa S, Ferroukhi H
    Transition to CASMO-5M and SIMULATE-3K for Stability Analyses of the Swiss BWRs
    Presented at: PHYSOR 2012: advances in reactor physics - linking research, industry, and education.
    DORA PSI
  • Dulla S, Picca P, Ravetto P, Canepa S
    Neural network and area method interpretation of pulsed experiments
    Presented at: International conference on the physics of reactors 2012: advances in reactor physics, PHYSOR 2012; April 15-20, 2012.
    DORA PSI
  • Fernandez-Moguel L
    Preliminary analysis of air ingress experiment QUENCH-16 using RELAP/SCDAPSim3.5 and MELCOR 1.8.6
    Presented at: 21st international conference nuclear energy for New Europe; September 5-7, 2012; Ljubljana.
    DORA PSI
  • Ferroukhi H, Vasiliev A, Dufresne A, Chawla R
    Towards a reference numerical scheme using MCNPX for PWR control rod tip fluence estimations
    In: PHYSOR 2012: advances in reactor physics. Vol. 1. La Grange Park, IL, USA: American Nuclear Society; 2012:401-417. https://www.ans.org/store/item-700371/.
    DORA PSI
  • Fiorina C, Aufiero M, Cammi A, Guerrieri C, Krepel J, Luzzi L, et al.
    Analysis of the MSFR core neutronics adopting different neutron transport models
    In: Proceedings of the 2012 20th international conference on nuclear engineering and the ASME 2012 power conference, ICONE 2012-POWER 2012. American Society of Mechanical Engineers (ASME); 2012:(10 pp.). https://doi.org/10.1115/ICONE20-POWER2012-54519
    DORA PSI
  • Fiorina C, Cammi A, Krepel J, Mikityuk K, Ricotti ME
    Preliminary analysis of the MSFR fuel cycle using modified-EQL3D procedure
    In: Vol. 4. International conference on nuclear engineering, proceedings, ICONE. American Society of Mechanical Engineers (ASME); 2012:293-302. https://doi.org/10.1115/ICONE20-POWER2012-54236
    DORA PSI
  • Girardin G, Alonso M, Mikityuk K
    Development of 3D full-core ERANOS-2.2/MCNPX-2.7.0 models and neutronic analysis of the BFS-2 zero-power facility
    In: International congress on advances in nuclear power plants 2012, ICAPP 2012. Vol. 3. ; 2012:1659-1667.
    DORA PSI
  • Grimm P, Perret G
    Experimental validation of CASMO-4E and CASMO-5M for radial fission rate distributions in a westinghouse SVEA-96 Optima2 BWR fuel assembly
    In: PHYSOR 2012: advances in reactor physics. Vol. 4. La Grange Park, IL, USA: American Nuclear Society; 2012:3410-3421. https://www.ans.org/store/item-700371/.
    DORA PSI
  • Grimm P, Vasiliev A, Wieselquist W, Ferroukhi H, Ledergerber G
    Reactor physics studies for assessment of tramp uranium methods
    In: Advances in reactor physics. Vol. 2. LaGrange Park, IL, USA: American Nuclear Society; 2012:1522-1535.
    DORA PSI
  • Hursin M, Perret G
    Design of a PROTEUS lattice representative of a burnt and fresh fuel interface at power conditions in light water reactors
    In: PHYSOR 2012: advances in reactor physics. Vol. 5. La Grange Park: American Nuclear Society; 2012:(12 pp.).
    DORA PSI
  • Hursin M, Koeberl O, Perret G
    Towards the reanalysis of void coefficients measurements at PROTEUS for High Conversion Light Water Reactor lattices
    In: PHYSOR 2012: advances in reactor physics. Vol. 3. La Grange Park, IL, USA: American Nuclear Society; 2012:2558-2568. https://www.ans.org/store/item-700371/.
    DORA PSI
  • Karanki DR, Dang VN, Kim T-W
    The impact of dynamics on the MLOCA accident model - an application of dynamic event trees
    In: 11th international probabilistic safety assessment and management conference and the annual european safety and reliability conference 2012. (PSAM11 ESREL 2012). Vol. 3. sine loco: IAPSAM; ESRA; 2012:2468-2479. https://www.iapsam.org/www.psam11.org/www/fi/index.php.html.
    DORA PSI
  • 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
  • Krack M
    Atomistic simulation of nuclear fuels
    In: Vol. 1383. Materials research society symposium proceedings. ; 2012:19-25. https://doi.org/10.1557/opl.2012.520
    DORA PSI
  • Langton SE, Buijs A, Zhu T, Novog DR
    Monte Carlo simulation of a burnup-averaged 78-element Canadian SCWR and similarity study with the ZED-2 test reactor
    In: 33rd annual conference of the Canadian nuclear society and 36th CNS/CNA student conference 2012. Building on our past.. building for the future. Vol. 2. ; 2012:1425-1429.
    DORA PSI
  • Miassoedov A, Tromm TW, Birchley J, Fichot F, Ma W, Pohlner G, et al.
    Corium and debris coolability studies performed in the severe accident research network of excellence (SARNET2)
    In: Vol. 2. International conference on nuclear engineering, proceedings, ICONE. American Society of Mechanical Engineers (ASME); 2012:383-392. https://doi.org/10.1115/ICONE20-POWER2012-54359
    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
  • Pelloni S, Mikityuk K
    Nuclear data uncertainty analysis for the generation IV gas-cooled fast reactor
    In: PHYSOR 2012: advances in reactor physics. Vol. 3. La Grange Park, IL, USA: American Nuclear Society; 2012:2592-2604. https://www.ans.org/store/item-700371/.
    DORA PSI
  • 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
  • Rycroft CH, Lind T, Güntay S, Dehbi A
    Granular flow in pebble bed reactors: dust generation and scaling
    In: Proceedings of ICAPP ‘12. ; 2012:12328 (9 pp.).
    DORA PSI
  • Sun K, Chenu A, Mikityuk K, Krepel J, Chawla R
    Coupled 3D-neutronics / thermal-hydraulics analysis of an unprotected loss-of-flow accident for a 3600 MWth SFR core
    In: PHYSOR 2012: advances in reactor physics. Vol. 4. La Grange Park, IL, USA: American Nuclear Society; 2012:3231-3245. https://www.ans.org/store/item-700371/.
    DORA PSI
  • Wieselquist W, Vasiliev A, Ferroukhi H
    Nuclear data uncertainty propagation in a lattice physics code using stochastic sampling
    In: PHYSOR 2012: advances in reactor physics. Vol. 4. La Grange Park, IL, USA: American Nuclear Society; 2012:3000-3015. https://www.ans.org/store/item-700371/.
    DORA PSI
  • Zhu T, Vasiliev A, Wieselquist W, Ferroukhi H
    Stochastic sampling method with MCNPX for nuclear data uncertainty propagation in criticality safety applications
    In: PHYSOR 2012: advances in reactor physics. Vol. 1. La Grange Park, IL, USA: American Nuclear Society; 2012:144-157. https://www.ans.org/store/item-700371/.
    DORA PSI
  • Karanki DR, Dang VN, Kim T-W
    Discrete dynamic event tree analysis of MLOCA using ADS-TRACE
    In: International topical meeting on probabilistic safety assessment and analysis (PSA 2011). Vol. 1. La Grange Park, IL, USA: American Nuclear Society; 2011:610-622. https://www.ans.org/store/item-700366/.
    DORA PSI
  • Khvostov G, Wiesenack W, Oberländer BC, Kolstad E, Ledergerber G, Zimmermann MA
    Post-test analysis of the Halden LOCA experiment IFA-650.7 using the Falcon code
    In: Proceedings of the enlarged Halden project group meeting, EHPG 2011. Halden, Norway: sine nomine; 2011:F2.2 (10 pp.).
    DORA PSI
  • Khvostov G, Kolstad E, Ledergerber G, Zimmermann MA, Wiesenack W, Brémond O, et al.
    Pre-calculation using the Falcon fuel behaviour code of the fuel rod design parameters and the test-conditions for a two-run Halden LOCA test with KKL BWR high-burnup fuel
    In: Enlarged Halden programme group meeting. Proceedings of the fuel & materials sessions. Vol. HPR-374. Halden, Norway: Institutt for Energiteknikk; 2011:F2.7 (21 pp.).
    DORA PSI
  • Khvostov G, Zimmermann MA, Lyon W, Pytel M
    Towards advanced modeling of MPS-assisted cladding failure during power ramps using the FALCON code
    Presented at: 2011 Water reactor fuel performance meeting/LWR/Top fuel; September 11-14, 2011; Chengdu, China.
    DORA PSI
  • Perret G, Jordan KA
    On the combination of delayed neutron and delayed gamma techniques for fission rate measurement in nuclear fuel
    In: ANIMMA 2011. Proceedings. 2nd international conference on advancements in nuclear instrumentation, measurement methods and their applications. International conference on advancements in nuclear Instrumentation measurement methods and their applications (ANIMMA). Piscataway: IEEE; 2011:(7 pp.). https://doi.org/10.1109/ANIMMA.2011.6172907
    DORA PSI
  • Yancey K, Mikityuk K, Krepel J, Chenu A
    Development and application of a comprehensive model of a lead-cooled fast reactor using the FAST code system
    In: Winter meeting 2011. Vol. 105. Transactions of the American Nuclear Society. La Grange Park: American Nuclear Society; 2011:699-700. https://www.ans.org/pubs/transactions/article-13076/.
    DORA PSI
  • Yun Y, Khvostov G, Freixa J, Zimmermann MA
    Analysis of fuel rod behaviour in a EPRTM during the base irradiation and LOCA-transient utilizing the FALCON code
    In: Proceedings of the 2010 LWR fuel performance/top fuel/WRFPM. sine loco: American Nuclear Society; 2011:345-353.
    DORA PSI
  • Zboray R, Guetg M, Kickhofel J, Prasser H-M
    Investigating annular flows and the effect of functional spacers in an adiabatic double-subchannel model of a BWR fuel bundle by ultra-fast X-ray Tomography
    Presented at: 14th international topical meeting on nuclear reactor thermalhydraulics, NURETH-14; September 25-30, 2011; Toronto, Ontario, Canada.
    DORA PSI
  • Zimmermann MA, Dang VN, Lanore J-M, Probst P, Hortal J, Amri A
    Insights from the SM2A pilot study towards quantification of a change of plant safety margin after a hypothetical power up-rate
    In: International topical meeting on probabilistic safety assessment and analysis (PSA 2011). Vol. 3. La Grange Park, IL, USA: American Nuclear Society; 2011:2281-2294. https://www.ans.org/store/item-700366/.
    DORA PSI
  • Aguirre C, Opel S, Ferroukhi H, Grandi G, Belblidia L, Thunman M, et al.
    Benchmarking of transient codes against cycle 19 stability measurements at Leibstadt nuclear power plant (KKL)
    In: International conference on the physics of reactors. Vol. 3. International Conference on the Physics of Reactors 2010, PHYSOR 2010. LaGrange Park: American Nuclear Society; 2010:2305-2321.
    DORA PSI
  • Bertolotto D, Manera A, Petrov V, Bissels WM, Prasser HM, Chawla R
    Set-up of a validation strategy for the coupled code CFX/TRACE in the FLORIS facility with the aid of CFD simulations
    In: Proceedings of ICAPP '10. Vol. 2. International congress on advances in nuclear power plants 2010, ICAPP 2010. La Grange Park: American Nuclear Society; 2010:1529-1537.
    DORA PSI
  • Chanaron B, Ahnert C, Bestion D, Zimmermann M, Cacuci D, Crouzet N
    The European project NURISP for nuclear reactor simulation
    In: Proceedings of the 2010 ANS annual meeting and embedded topical meeting: isotopes for medicine and industry. Vol. 103. Transactions of the American nuclear society. sine loco: sine nomine; 2010:671-672.
    DORA PSI
  • Chawla R, Girardin G, Joneja OP
    Reactor experiments course of the Swiss Nuclear Engineering master
    In: Proceedings of the 18th international conference on nuclear engineering, ICONE18. Vol. 2. International conference on nuclear engineering, proceedings, ICONE. New York: American Society of Mechanical Engineers; 2010:323-330. https://doi.org/10.1115/ICONE18-29183
    DORA PSI
  • Chawla R, Ansermet JP, Cavedon JM, Hirt P, Kröger W, Prasser HM, et al.
    The Swiss master in nuclear engineering: a collaboration between universities, research centre and industry
    In: 18th international conference on nuclear engineering. Vol. 2. international conference on nuclear engineering, proceedings, ICONE. New York City: American Society of Mechanical Engineers; 2010. https://doi.org/10.1115/ICONE18-29218
    DORA PSI
  • Chenu A, Mikityuk K, Chawla R
    A coupled 3D neutron kinetics/thermal-hydraulics model of the generation IV sodium-cooled fast reactor
    In: Proceedings of ICAPP '10. Vol. 2. International congress on advances in nuclear power plants 2010, ICAPP 2010. sine loco: sine nomine; 2010:1331-1337.
    DORA PSI
  • Chenu A, Mikityuk K, Chawla R
    Modeling of friction pressure drop for sodium two-phase flow in round tubes
    In: Proceedings of ICAPP '10. Vol. 3. International congress on advances in nuclear power plants 2010, ICAPP 2010. sine loco: sine nomine; 2010:1637-1644.
    DORA PSI
  • Dang VN, Kim T-W, Zimmermann MA, Manera A
    Assessing safety margins: the impact of a power uprate on risk from small and medium LOCA scenarios
    In: 10th international conference on probabilistic safety assessment & management, PSAM10. Vol. 1. sine loco: IAPSAM; ESRA; 2010:83-92. https://www.iapsam.org/psam10/index.html.
    DORA PSI
  • Ferroukhi H, Hofer K
    Coupled 3-D neutronics/thermal-hydraulic core analysis of a BWR nuclear heating transient
    In: Proceedings of the international conference on the physics of reactors 2010 (PHYSOR 2010). Vol. 3. International conference on the physics of reactors 2010, PHYSOR 2010. La Grange Park: American Nuclear Society; 2010:2422-2436.
    DORA PSI
  • Girardin G, Epiney A, Mikityuk K, Chawla R
    Neutronic analysis of water-steam injection accidents for generation IV gas-cooled fast reactors
    In: International conference on the physics of reactors 2010. Vol. 3. American Nuclear Society; 2010:1843-1855.
    DORA PSI
  • Giust FD, Grimm P, Chawla R
    Experimental comparisons of 3D reconstructed pin-power distributions in full-scale BWR fuel assemblies
    In: Proceedings of the 18th international conference on nuclear engineering, ICONE18. Vol. 2. International conference on nuclear engineering, proceedings, ICONE. New York: American Society of Mechanical Engineers; 2010:ICONE18-29691 (10 pp.). https://doi.org/10.1115/ICONE18-29691
    DORA PSI
  • Ivanova T, Fernex F, Kolbe E, Vasiliev A, Lee GS, Woo SW, et al.
    OECD/NEA expert group on uncertainty analysis for criticality safety assessment: current activities
    In: Advances in reactor physics to power the nuclear renaissance. Vol. 3. International conference on the physics of reactors 2010, PHYSOR 2010. La Grange Park: American Nuclear Society; 2010:2212-2226.
    DORA PSI
  • 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
  • Khvostov G, Zimmermann MA, Ledergerber G
    Parametric study of fuel rod behaviour during the RIA using the modified FALCON code
    In: Nuclear fuel behaviour during reactivity initiated accidents. Workshop proceedings. sine loco: OECD; 2010:247-258.
    DORA PSI
  • Krepel J, Sun K, Pelloni S, Pilarski S, Mikityuk K
    Comparison of closed fuel cycles for generation-IV fast reactors by means of the equilibrium procedure EQL3D
    In: Proceedings of ICAPP '10. ; 2010:785-794.
    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
  • Nikitin K, Judd J, Grandi GM, Manera A, Ferroukhi H
    Peach bottom 2 turbine trip 2 simulation by TRACE/S3K coupled code
    In: International conference on the physics of reactors 2010. Vol. 3. International conference on the physics of reactors 2010, PHYSOR 2010. La Grange Park: American Nuclear Society; 2010:2283-2293.
    DORA PSI
  • Petrov V, Manera A
    Development and validation of a CFD model for the EPR™ pressure vessel
    In: Proceedings of ICAPP '10. Vol. 3. International congress on advances in nuclear power plants 2010, ICAPP 2010. La Grange Park: American Nuclear Society; 2010:1685-1691.
    DORA PSI
  • Rineiski A, Rimpault G, Glinatsis G, Messaoudi N, Pelloni S, Schwenk-Ferrero A, et al.
    Decay heat benchmark for uranium-free fuels with Minor Actinides
    In: Proceedings of the 18th international conference on nuclear engineering, ICONE18. Vol. 2. International conference on nuclear engineering, proceedings, ICONE. New York: American Society of Mechanical Engineers; 2010:ICONE18-29654 (10 pp.). https://doi.org/10.1115/ICONE18-29654
    DORA PSI
  • 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
  • Sun K, Krepel J, Mikityuk K, Chawla R
    Void reactivity decomposition for the sodium-cooled fast reactor in equilibrium closed fuel cycle
    In: Proceedings of the international conference on the physics of reactors 2010 (PHYSOR 2010). Vol. 3. International conference on the physics of reactors 2010, PHYSOR 2010. La Grange Park: American Nuclear Society; 2010:1779-1790.
    DORA PSI
  • Vasiliev A, Pittarello R, Ferroukhi H, Kolbe E
    Verification of PWR in- and ex- vessel neutron fluence calculations with MCNPX, based on the "H.B. Robinson-2" dosimetry benchmark
    In: Proceedings of the international conference on the physics of reactors. Vol. 1. International conference on the physics of reactors 2010, PHYSOR 2010. La Grange Park: American Nuclear Society; 2010:838-847.
    DORA PSI
  • Wieselquist WA
    A low-order quasidiffusion discretization via linear-continuous finite-elements on unstructured triangular meshes
    In: International conference on the physics of reactors 2010. Vol. 1. American Nuclear Society; 2010:182-197.
    DORA PSI

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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    Modeling of sodium two-phase flow with the trace code
    In: Proceedings of the 17th international conference on nuclear engineering, ICONE17. Vol. 1. International conference on nuclear engineering, proceedings, ICONE. New York: American Society of Mechanical Engineers; 2009:803-811. https://doi.org/10.1115/ICONE17-75131
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    Three-dimensional core behaviour analysis of the Gas-cooled Fast Reactor (GFR) during hypothetical control assembly withdrawal accidents
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    A dynamic model for fission gas release and gaseous swelling integrated into the FALCON fuel analysis and licensing code
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    Assessment of S(α,β) libraries for criticality safety evaluations of wet storage pools by refined trend analyses
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    Comparison of reconstructed radial pin total fission rates with experimental results in full scale BWR fuel elements
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    Analysis of reactivity worths of highly-burnt PWR fuel samples measured in LWR-PROTEUS Phase II
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    Impact of newly-measured gadolinium cross sections on BWR fuel rod reaction rate distributions
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    MCNP analysis of generic configurations in the context of the LIFE@PROTEUS experiments
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    EQL3D: Methodology for simulation of equilibrium cycle for advanced fast reactors
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    On the observation of discrepancies in the 16O(n,α) data between different evaluated nuclear data files
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  • Vasiliev A, Ferroukhi H, Kolbe E, Zimmermann MA
    On the use of importance factors from Monte Carlo calculations for efficient fast neutron fluence prediction
    In: Proceedings of the international conference on the physics of reactors "nuclear power: a sustainable resource". Vol. 2. International conference on the physics of reactors 2008, PHYSOR 08. Villigen: Paul Scherrer Institut; 2008:856-863.
    DORA PSI
  • Vinai P, Macian-Juan R, Chawla R
    Propagation of void fraction uncertainly measures in the RETRAN-3D simulation of the Peach Bottom turbine trip
    In: International conference on the physics of reactors “nuclear power: a sustainable resource”. ; 2008:(8 pp.).
    DORA PSI
  • Zerkak O, Ferroukhi H
    Effects of the core inlet mixing modelling on a main steam line break analysis at hot full power
    In: Proceedings of the international conference on the physics of reactors "nuclear power: a sustainable resource". Vol. 3. International conference on the physics of reactors 2008, PHYSOR 08. Villigen: Paul Scherrer Institut; 2008:1943-1950.
    DORA PSI
  • Barten W, Manera A, Macian-Juan R
    Assessment of the capability of the trace code to model the propagation of linear acoustic pressure waves in one-dimensional flows
    In: 12th international topical meeting on nuclear reactor thermal hydraulics (NURETH-12). Westmont: American Nuclear Society; 2007:652-665.
    DORA PSI
  • Ferroukhi H, Hollard JM, Zerkak O, Coddington P
    PWR cell calculations using APOLLO-2 within the NURESIM benchmark framework
    In: Vol. 97. Transactions of the American Nuclear Society. Westmont: American Nuclear Society; 2007:703-704. https://www.ans.org/pubs/transactions/article-7751/.
    DORA PSI
  • Hellwig C, Horvath MI, Blair PR, Chawla R, Günther D
    Fission gas distribution and behavior in the high burn-up structure
    In: LWR fuel performance meeting/top fuel 2007. Westmont: American Nuclear Society; 2007:291-300.
    DORA PSI
  • Khvostov G, Romano A, Zimmermann MA
    Modeling the effects of axial fuel relocation in the IFA-650.4 LOCA test
    Presented at: Enlarged Halden programme group meeting 2007; March 11-16, 2007; Storefjell, Norway.
    DORA PSI
  • Manera A, Macian R
    Assessment of trace film condensation models with and without non-condensable gases
    In: 12th international topical meeting on nuclear reactor thermal hydraulics (NURETH-12). Westmont: American Nuclear Society; 2007:254-268.
    DORA PSI
  • Rohde M, Marcel CP, Manera A, van der Hagen THJJ, Shiralkar B
    Experimental and numerical investigations on the ESBWR stability performance
    In: 12th international topical meeting on nuclear reactor thermal hydraulics (NURETH-12). Westmont: American Nuclear Society; 2007:099 (20 pp.).
    DORA PSI
  • Salvatores M, Boucher L, Meyer M, Morel D, Na B, Schwenk-Ferrero A, et al.
    Scenarios for P/T implementation in Europe within a regional approach
    In: 7th international conference on advanced nuclear fuel cycles and systems. GLOBAL 2007. Westmont: American Nuclear Society; 2007:304-309.
    DORA PSI
  • Zboray R, Manera A, Niceno B, Prasser H-M
    Investigations on mixing phenomena in single-phase flows in a T-junction geometry
    In: 12th international topical meeting on nuclear reactor thermal hydraulics (NURETH-12). Westmont: American Nuclear Society; 2007:830-849.
    DORA PSI
  • Zerkak O, Coddington P, Crouzet N, Royer E, Jimenez J, Cuervo D
    LWR multi-physics developments and applications within the framework of the NURESIM European project
    In: Joint international topical meeting on mathematics & computations and supercomputing in nuclear applications (M & C + SNA 2007). Vol. 4. La Grange Park: American Nuclear Society; 2007:2178-2199.
    DORA PSI
  • Bubelis E, Coddington P, Leung W
    Pre-test analysis of the MEGAPIE spallation source target cooling loop using the TRAC/AAA code
    In: Proceedings of ICAPP '06. Vol. 2006. Proceedings of the 2006 international congress on advances in nuclear power plants, ICAPP'06. La Grange Park: American Nuclear Society; 2006:452-461.
    DORA PSI
  • Caruso S, Murphy M, Jatuff F, Chawla R
    Non-invasive characterization of burnup for PWR spent fuel rods with burnups > 80 GWd/t
    In: Proceedings of ICAPP '06. Vol. 2006. Proceedings of the 2006 international congress on advances in nuclear power plants, ICAPP'06. La Grange Park: American Nuclear Society; 2006:2020-2027.
    DORA PSI
  • Girardin G, Pelloni S, Coddington P, Chawla R
    Comparative analysis of the reference GCFR-PROTEUS MOX lattice with MCNPX-25e and ERANOS-2.0 in conjunction with modern nuclear data libraries
    In: PHYSOR 2006 : advances in nuclear analysis and simulation : American nuclear society's topical meeting on reactor physics. Vol. 2006. PHYSOR-2006 - American nuclear society's topical meeting on reactor physics. La Grange: American Nuclear Society; 2006:(9 pp.).
    DORA PSI
  • Grimm P, Günther-Leopold I, Kobler Waldis J, Berger HD, Krouthén J
    Burnup calculations and chemical analysis of irradiated fuel samples studied in LWR-PROTEUS phase II
    In: PHYSOR-2006 - American nuclear society's topical meeting on reactor physics. Advances in nuclear analysis and simulation. Vol. 2006. PHYSOR-2006 - American nuclear society's topical meeting on reactor physics. La Grange: American Nuclear Society; 2006:(3 pp.).
    DORA PSI
  • Jasiulevicius A, Macian-Juan R
    Impact of different correlations on TRACEv4.160 predicted critical heat flux
    In: Proceedings of ICAPP '06. Vol. 2006. Proceedings of the 2006 international congress on advances in nuclear power plants, ICAPP'06. La Grange Park: American Nuclear Society; 2006:1608-1615.
    DORA PSI
  • Jasiulevicius A, Zerkak O, Macian-Juan R
    Investigation of heat transfer mechanisms under shutdown plant conditions with TRACEv4.160
    In: Proceedings of ICAPP'06. Vol. 2006. Proceedings of the 2006 international congress on advances in nuclear power plants, ICAPP'06. La Grange Park: American Nuclear Society; 2006:1820-1828.
    DORA PSI
  • Jasiulevicius A, Macian-Juan R
    Predictions of critical heat flux in annular pipes with TRACE V4.160 code
    In: International conference on nuclear engineering, proceedings, ICONE. Vol. 2006. International conference on nuclear engineering, proceedings, ICONE. New York: American Society of Mechanical Engineers; 2006:243-250. https://doi.org/10.1115/ICONE14-89253
    DORA PSI
  • Jasiulevicius A, Macian-Juan R
    Steady state film boiling heat transfer simulated with trace V4.160
    In: Proceedings of ICONE 14. Vol. 2006. International conference on nuclear engineering, proceedings, ICONE. New York: American Society of Mechanical Engineers; 2006:531-539. https://doi.org/10.1115/ICONE14-89494
    DORA PSI
  • Kolbe E, Vasiliev A, Zimmermann MA
    Assessment of standard point-wise neutron data libraries for criticality safety analysis with a Monte Carlo code
    In: Proceedings of the American nuclear society's topical meeting on reactor physics. Vol. 2006. PHYSOR-2006 - American nuclear society's topical meeting on reactor physics. La Grange Park: American Nuclear Society; 2006:D081 (10 pp.).
    DORA PSI
  • Lebrat JF, Plaschy M, Tommasi J, Suteau C, Plisson-Rieunier D, De Saint Jean C
    Comparative analysis of selected aspects of the muse-4 experiments with the JEF-2.2 and JEFF-3.1 libraries
    In: Vol. 2006. PHYSOR-2006 - American nuclear society's topical meeting on reactor physics. La Grange Park: American Nuclear Society; 2006:3052-3061.
    DORA PSI
  • Mitchell C, Poette C, Peers K, Coddington P, Somers J, Van-Goethem G
    GCFR: the European Union's gas cooled fast reactor project
    In: Proceedings of ICAPP '06. Vol. 2006. Proceedings of the 2006 international congress on advances in nuclear power plants, ICAPP'06. La Grange Park: American Nuclear Society; 2006:540-548.
    DORA PSI
  • Murphy MF, Plaschy M, Jatuff F, Bergmann U, Chawla R
    Fission and capture rate measurements in a SVEA-96 optima2 BWR assembly compared with MCNPX predictions
    In: American nuclear society's topical meeting on reactor physics. Vol. 2006. PHYSOR-2006 - American nuclear society's topical meeting on reactor physics. La Grange: American Nuclear Society; 2006:1169-1176.
    DORA PSI
  • Petkevich P, Mikityuk K, Coddington P, Pelloni S, Chawla R
    Comparative transient analysis of a gas-cooled fast reactor for different fuel types
    In: Proceedings of ICAPP '06. Vol. 2006. Proceedings of the 2006 international congress on advances in nuclear power plants, ICAPP'06. La Grange Park: American Nuclear Society; 2006:549-559.
    DORA PSI
  • Plaschy M, Destouches C, Chawla R, Beretz D, Mellier F, Servière H, et al.
    Determination of adjusted neutron spectra in different MUSE configurations by unfolding techniques
    In: Vehar DW, Gilliam DG, Adams JM, eds. Reactor dosimetry. 12th international symposium. Vol. 1490. West Conshohocken, PA: ASTM International; 2006:55-65. https://doi.org/10.1520/STP45426S
    DORA PSI
  • Plaschy M, Murphy M, Jatuff F, Seiler R, Chawla R
    Experimental critical loadings and control rod worths in LWR-PROTEUS configurations compared with MCNPX results
    In: PHYSOR 2006 : advances in nuclear analysis and simulation : American nuclear society's topical meeting on reactor physics. Vol. 2006. PHYSOR-2006 - American nuclear society's topical meeting on reactor physics. La Grange: American Nuclear Society; 2006:A093 (10 pp.).
    DORA PSI
  • Vasiliev A, Ferroukhi H, Zimmermann MA
    CASMO-4/SIMULATE-3/MCNPX analysis of a reactor pressure vessel scraping test
    In: Proceedings of the American nuclear society's topical meeting on reactor physics. Vol. 2006. PHYSOR-2006 - American nuclear society's topical meeting on reactor physics. La Grange Park: American Nuclear Society; 2006:B136 (10 pp.).
    DORA PSI
  • Vinai P, Macian R, Chawla R
    A methodology for the quantification of uncertainty in best estimate code physical models
    In: Proceedings of ICAPP '06. Vol. 2006. Proceedings of the 2006 international congress on advances in nuclear power plants, ICAPP'06. La Grange Park: American Nuclear Society; 2006:1087-1098.
    DORA PSI
  • Vollaire J, Plaschy M, Jatuff F, Chawla R
    Determination of 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
  • da Cruz DF, Hogenbirk A, Bosq JC, Rimpault G, Prulhiere G, Morris P, et al.
    Neutronic benchmark on the 2400 MW gas-cooled fast reactor design
    In: PHYSOR 2006 : advances in nuclear analysis and simulation : American nuclear society's topical meeting on reactor physics. Vol. 2006. PHYSOR-2006 - American nuclear society's topical meeting on reactor physics. La Grange: American Nuclear Society; 2006:D126 (10 pp.).
    DORA PSI

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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

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