Conference Articles

2017

  • Aounallah Y
    Post-dryout heat transfer assessment of trace
    In: 37th annual conference of the canadian nuclear society and 41st annual cns/cna student conference. Canadian Nuclear Society; 2017.
    DORA PSI
  • Aounallah Y
    Simulations with TRACE of a BWR/4 steam line break under "hot standby" conditions
    In: 37th annual conference of the canadian nuclear society & 41st CNS/CNA student conference 2017. Vol. 1. Toronto, Ontario, Canada: Canadian Nuclear Society; 2017:218-228.
    DORA PSI
  • Aounallah Y
    TRACE/S3K code coupling simulations of a BWR/4 anticipated transient without scram
    In: Proceedings of the 37th annual conference of the Canadian Nuclear Society & 41st CNS/CNA student conference 2017. Vol. 2. Toronto: Canadian Nuclear Society (CNS); 2017:1000-1013.
    DORA PSI
  • Chionis D, Dokhane A, Belblidia L, Pecchia M, Giardin G, Ferroukhi H, et al.
    SIMULATE-3K analyses of neutron noise response to fuel assembly vibrations and thermal-hydraulics parameters fluctuations
    In: Proceedings of the international conference on mathematics & computational methods applied to nuclear science & engineering (M&C 2017). Daejeon: Korean Nuclear Society; 2017:P289 (8 pp.).
    DORA PSI
  • Chollet M, Cozzo C, Bertsch J, Martin M, Grolimund D, Samson V-A
    New insights in the fuel grain subdivision during in-plant irradiation up to high burn-up
    Presented at: Water reactor fuel performance meeting 2017 (WRFPM 2017); September 10-14, 2017; Jeju, Korea.
    DORA PSI
  • Coindreau O, Jäckel B, Rocchi F, Alcaro F, Angelova D, Bandini G, et al.
    Severe accident code-to-code comparison for two accident scenarios in a spent fuel pool
    Presented at: 8th European review meeting on severe accident research (ERMSAR 2017); May 16-18, 2017; Warsaw, Poland.
    DORA PSI
  • Cozzo C, Bertsch J, Fave L, Rahman S, Dokhane A, Krack M, et al.
    SiC cladding behavior: experiments and modelling at PSI
    Presented at: Water reactor fuel performance meeting 2017 (WRFPM 2017); September 10-14, 2017; Jeju, Korea.
    DORA PSI
  • Dehbi A, Kelm S, Kalilainen J, Mueller H
    The influence of thermal radiation on the free convection inside enclosures
    Presented at: 8th European review meeting on severe accident research (ERMSAR 2017); May 16-18, 2017; Warsaw, Poland.
    DORA PSI
  • Dokhane A, Grandi G, Leray O, Rochman D, Vasiliev A, Ferroukhi H
    Nuclear data uncertainty decomposition for SPERT-III RIA experiments using SIMULATE-3K and SHARK-X
    In: Proceedings of the international conference on mathematics & computational methods applied to nuclear science & engineering (M&C 2017). Daejeon: Korean Nuclear Society; 2017:P236 (8 pp.).
    DORA PSI
  • Fischer U, Angelone M, Avrigeanu M, Avrigeanu V, Bachmann C, Dzysiuk N, et al.
    The role of nuclear data for fusion nuclear technology
    Presented at: International symposium on fusion nuclear technology; September 25-29, 2017; Kyoto, Japan.
    DORA PSI
  • Fleming M, Sublet J-C, Gilbert MR, Koning A, Rochman D
    TALYS/TENDL verification and validation processes: Outcomes and recommendations
    In: Plompen A, Hambsch F-J, Schillebeeckx P, Mondelaers W, Heyse J, Kopecky S, et al., eds. ND 2016: international conference on nuclear data for science and technology. Vol. 146. EPJ web of conferences. sine loco: EDP Sciences; 2017:02033 (4 pp.). https://doi.org/10.1051/epjconf/201714602033
    DORA PSI
  • Griffin P, Rochman D, Koning A
    Characterization of the energy-dependent uncertainty and correlation in silicon neutron displacement damage metrics
    In: Plompen A, Hambsch F-J, Schillebeeckx P, Mondelaers W, Heyse J, Kopecky S, et al., eds. ND 2016: international conference on nuclear data for science and technology. Vol. 146. EPJ web of conferences. sine loco: EDP Sciences; 2017:02008 (6 pp.). https://doi.org/10.1051/epjconf/201714602008
    DORA PSI
  • Herrero JJ, Rochman D, Leray O, Vasiliev A, Pecchia M, Ferroukhi H, et al.
    Impact of nuclear data uncertainty on safety calculations for spent nuclear fuel geological disposal
    In: Plompen A, Hambsch F-J, Schillebeeckx P, Mondelaers W, Heyse J, Kopecky S, et al., eds. ND 2016: international conference on nuclear data for science and technology. Vol. 146. EPJ web of conferences. sine loco: EDP Sciences; 2017:09028 (4 pp.). https://doi.org/10.1051/epjconf/201714609028
    DORA PSI
  • Hursin M, Leray O, Perret G, Pautz A, Bostelmann F, Aures A, et al.
    Impact of implicit effects on uncertainties and sensitivities of the Doppler coefficient of a LWR pin cell
    In: Plompen A, Hambsch F-J, Schillebeeckx P, Mondelaers W, Heyse J, Kopecky S, et al., eds. ND 2016: international conference on nuclear data for science and technology. Vol. 146. EPJ web of conferences. sine loco: EDP Sciences; 2017:09034 (5 pp.). https://doi.org/10.1051/epjconf/201714609034
    DORA PSI
  • Jaeckel B, Steiner P, Klügel J-U
    Progression of postulated loss-of-cooling accidents in the wet storage pool of NPP Gösgen/Däniken
    In: Proceedings of NENE 2017. Ljubljana: Nuclear Society of Slovenia; 2017:402.1 (8 pp.).
    DORA PSI
  • Leray O, Rochman D, Fleming M, Sublet J-C, Koning A, Vasiliev A, et al.
    Fission yield covariances for JEFF: a Bayesian Monte Carlo method
    In: Plompen A, Hambsch F-J, Schillebeeckx P, Mondelaers W, Heyse J, Kopecky S, et al., eds. ND 2016: international conference on nuclear data for science and technology. Vol. 146. EPJ web of conferences. sine loco: EDP Sciences; 2017:09023 (4 pp.). https://doi.org/10.1051/epjconf/201714609023
    DORA PSI
  • Mala P, Pautz A, Canepa S, Ferroukhi H
    Nodal and pin-by-pin calculations comparison with codes SIMULATE-5 and DYN3D
    In: Proceedings of the international conference on mathematics & computational methods applied to nuclear science & engineering (M&C 2017). Daejeon: Korean Nuclear Society; 2017:P010 (9 pp.).
    DORA PSI
  • Mukin R, Clifford I, Ferroukhi H, Seidl M
    Thermal hydraulic analysis of PWR assembly bowing using subchannel code COBRA-TF
    Presented at: 17th international topical meeting on nuclear reactor thermal hydraulics (NURETH 2017); September 3-8, 2017; Xi'an, China.
    DORA PSI
  • Mukin R, Puragliesi R, Ceuca SC, Austregesilo H, Bousbia Salah A
    Thermal mixing assessment using 3-D thermal-hydraulic and CFD codes
    Presented at: 17th international topical meeting on nuclear reactor thermal hydraulics (NURETH 2017); September 3-8, 2017; Xi'an, China.
    DORA PSI
  • Palmiotti G, Salvatores M, Hursin M, Kodeli I, Gabrielli F, Hummel A
    New approaches to provide feedback from nuclear and covariance data adjustment for effective improvement of evaluated nuclear data files
    In: Plompen A, Hambsch F-J, Schillebeeckx P, Mondelaers W, Kopecky S, Siegler P, et al., eds. ND 2016: international conference on nuclear data for science and technology. Vol. 146. EPJ web of conferences. sine loco: EDP Sciences; 2017:06003 (11 pp.). https://doi.org/10.1051/epjconf/201714606003
    DORA PSI
  • Rochman D, Mala P, Ferroukhi H, Vasiliev A, Seidl M, Janin D, et al.
    Bowing effects on power and burn-up distributions for simplified full PWR and BWR cores
    In: Proceedings of the international conference on mathematics & computational methods applied to nuclear science & engineering (M&C 2017). Daejeon: Korean Nuclear Society; 2017:P286 (7 pp.).
    DORA PSI
  • Rochman D, Koning AJ, Sublet JC, Fleming M, Bauge E, Hilaire S, et al.
    The TENDL library: hope, reality and future
    In: Plompen A, Hambsch F-J, Schillebeeckx P, Mondelaers W, Heyse J, Kopecky S, et al., eds. ND 2016: international conference on nuclear data for science and technology. Vol. 146. EPJ web of conferences. sine loco: EDP Sciences; 2017:02006 (5 pp.). https://doi.org/10.1051/epjconf/201714602006
    DORA PSI
  • Rýdl A, Lind T, Fernandez-Moguel L
    Modeling of fission roduct scrubbing in experiments and in integral severe accident scenarios
    Presented at: 8th European review meeting on severe accident research (ERMSAR 2017); May 16-18, 2017; Warsaw, Poland.
    DORA PSI
  • Siefman DJ, Hursin M, Grimm P, Pautz A
    Case study of data assimilation methods with the LWR-Proteus Phase II experimental campaign
    In: Proceedings of the international conference on mathematics & computational methods applied to nuclear science & engineering (M&C 2017). Daejeon: Korean Nuclear Society; 2017:(10 pp.).
    DORA PSI
  • Sjöstrand H, Conroy S, Helgesson P, Hernandez SA, Koning A, Pomp S, et al.
    Propagation of nuclear data uncertainties for fusion power measurements
    In: Plompen A, Hambsch F-J, Schillebeeckx P, Mondelaers W, Heyse J, Kopecky S, et al., eds. ND 2016: international conference on nuclear data for science and technology. Vol. 146. EPJ web of conferences. sine loco: EDP Sciences; 2017:02034 (4 pp.). https://doi.org/10.1051/epjconf/201714602034
    DORA PSI

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

Analysis of Oxidation and Nitriding Experiments of Zircaloy-4 Cladding
B.S. Jäckel, S. Park, L. Fernandez-Moguel
2nd NuFuel Conference, Lecco, Italy

Droplet Size Estimation inside a Self-Priming Venturi Scrubber by Shadowgraphy
L. Perez, P. Papadopoulos, H.-M. Prasser
ENYGF, Manchester, UK

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