Conference Articles

2018

  • Andreani M, Kapulla R
    Analyses of gas stratification erosion by a vertical jet in presence of an obstacle using the GOTHIC code
    In: Proceedings of the 26th international conference on nuclear engineering (ICONE26). Thermal hydraulics and safety analyses. Vol. 6B. New York: American Society of Mechanical Engineers (ASME); 2018:ICONE26-82360 (11 pp.). https://doi.org/10.1115/ICONE26-82360
    DORA PSI
  • Beghi I, Tietze S, Lind T, Prasser H-M
    Effect of hydrodynamics on the retention of iodine in a wet scrubber
    In: International congress on advances in nuclear power plants (ICAPP 2018). Vol. 1. Illinois: American Nuclear Society; 2018:302-309.
    DORA PSI
  • Casanovas A, Domingo-Pardo C, Guerrero C, Lerendegui-Marco J, Calviño F, Tarifeño-Saldivia A, et al.
    Measurement of the radiative capture cross section of the s-process branching points 204Tl and 171Tm at the n_TOF facility (CERN)
    In: Sun Y, ed. 16th international symposium on capture gamma-ray spectroscopy and related topics (CGS16). Vol. 178. EPJ web of conferences. sine loco: EDP Sciences; 2018:03004 (5 pp.). https://doi.org/10.1051/epjconf/201817803004
    DORA PSI
  • Chionis D, Dokhane A, Ferroukhi H, Girardin G, Pautz A
    PWR neutron noise phenomenology: part I - simulation of stochastic phenomena with simulate-3K
    In: Proceedings of the PHYSOR 2018. LaGrange Park, IL, USA: American Nuclear Society; 2018:1001-1012.
    DORA PSI
  • Chionis D, Dokhane A, Ferroukhi H, Girardin G, Pautz A
    PWR neutron noise phenomenology: part II - qualitative comparison against plant data
    In: Proceedings of the PHYSOR 2018. LaGrange Park, IL, USA: American Nuclear Society; 2018:1013-1024.
    DORA PSI
  • Cozzo C, Khvostov G
    ATF developments in FALCON V1 at PSI
    In: Topfuel 2018. Part 4. Brussels: European Nuclear Society; 2018:A0112 (9 pp.).
    DORA PSI
  • De Sousa Ribeiro F, Calivá F, Chionis D, Dokhane A, Mylonakis A, Demazière C, et al.
    Towards a deep unified framework for nuclear reactor perturbation analysis
    In: Sundaram S, ed. Proceedings of the 2018 IEEE symposium series on computational intelligence (SSCI 2018). Piscataway: IEEE; 2018:120-127. https://doi.org/10.1109/SSCI.2018.8628637
    DORA PSI
  • Dokhane A, Vasiliev A, Rochman D, Ferroukhi H, Grandi G
    Analyses of the SPERT-III RIA experiments with nuclear data uncertainty quantification using three different covariance matrix libraries
    In: Proceedings of the PHYTRA4 conference. sine loco: American Nuclear Society (ANS); 2018:91-102.
    DORA PSI
  • Griffin PJ, Koning A, Rochman D
    Importance of treating correlations in the uncertainty quantification of radiation damage metrics
    In: Radiation protection and shielding division 20th topical meeting. Illinois: American Nuclear Society (ANS); 2018:(10 pp.).
    DORA PSI
  • Hursin M, Siefman D, Perret G, Rochman D, Vasiliev A, Ferroukhi H
    Determination of sobol sensitivity indices for correlated inputs with SHARK-X
    In: Proceedings of the PHYSOR 2018. LaGrange Park, IL, USA: American Nuclear Society; 2018:(12 pp.).
    DORA PSI
  • Hursin M, Siefman D, Perret G, Pautz A
    Representativity analysis of the LWR-PROTEUS Phase II experiments using SHARKX stochastic sampling method
    Presented at: ANS best estimate plus uncertainty international conference (BEPU 2018); May 13-18, 2018; Lucca, Italy.
    DORA PSI
  • Jäckel BS, Lind T, Fernandez-Moguel L, Steinbrück M, Park S
    Development of a computer code model for nitriding and re‐oxidation of cladding materials under severe accident conditions
    In: Proceedings of the international conference nuclear energy for New Europe (NENE 2018). Ljubljana: Nuclear Society of Slovenia; 2018:506.1 (8 pp.).
    DORA PSI
  • Kalilainen J, Kim H, Dehbi A, Lind T
    Aerosol depletion in natural circulation in simplified geometry
    In: International congress on advances in nuclear power plants (ICAPP 2018). Vol. 1. Illinois: American Nuclear Society; 2018:571-577.
    DORA PSI
  • Kalilainen J, Lind T, Prasser H-M
    Loss of forced cooling accident analysis of HTR-PM using MELCOR 2.2 code
    In: Proceedings of HTR 2018. sine loco: sine nomine; 2018:(7 pp.).
    DORA PSI
  • Kromer H, Adams R, Soubelet B, Zboray R, Prasser HM
    Improvement of a compact fast neutron generator for imaging applications
    In: 2018 IEEE nuclear science symposium and medical imaging conference proceedings (NSS/MIC). sine loco: IEEE; 2018:(3 pp.). https://doi.org/10.1109/NSSMIC.2018.8824470
    DORA PSI
  • Lamirand V, Perret G, Radman S, Siefman D, Frajtag P, Hursin M, et al.
    Design of separated element reflector experiments in CROCUS: PETALE
    In: Sparks MH, DePriest KR, Vehar DW, eds. Reactor dosimetry: 16th international symposium. West Conshohocken, USA: ASTM International; 2018:1-14. https://doi.org/10.1520/STP160820170090
    DORA PSI
  • Lamirand V, De Izzarra G, Krasa A, Perret G, Pakari O, Frajtag P, et al.
    Intercomparison of neutron noise measurement systems in the CROCUS reactor
    In: Proceedings of the PHYSOR 2018. LaGrange Park, IL, USA: American Nuclear Society; 2018:(11 pp.).
    DORA PSI
  • Mukin R, Clifford I, Ferroukhi H, Niffenegger M
    Pressurized Thermal Shock (PTS) transient scenarios analysis with TRACE
    In: Proceedings of the 26th international conference on nuclear engineering (ICONE26). Thermal hydraulics and safety analyses. New York: American Society of Mechanical Engineers (ASME); 2018:ICONE26-81749 (7 pp.). https://doi.org/10.1115/ICONE26-81749
    DORA PSI
  • Mukin R, Seidl M, Clifford I, Ferroukhi H
    Sensitivity of CTF solution to subchannel window size
    In: Proceedings of the 26th international conference on nuclear engineering (ICONE26). Thermal hydraulics and safety analyses. New York: American Society of Mechanical Engineers (ASME); 2018:ICONE26-82546 (11 pp.). https://doi.org/10.1115/ICONE26-82546
    DORA PSI
  • Ngayam-Happy R, Cozzo C, Khvostov G, Krack M, Ferroukhi H
    Fuel thermo-mechanical simulations with uncertainty quantification and sensitivity analysis of the OECD/NEA RIA code benchmark using FALCON and URANIE
    Presented at: ANS Best estimate plus uncertainty International conference (BEPU 2018); May 13-18, 2018; Lucca, Italy.
    DORA PSI
  • Pakari O, Lamirand V, Perret G, Braun L, Frajtag P, Pautz A
    Current mode neutron noise measurements in the zero power reactor CROCUS
    In: Lyoussi A, Carette M, Giot M, Le Dû P, Reynard-Carette C, Schyns M, et al., eds. ANIMMA 2017 - advancements in nuclear instrumentation measurement methods and their applications. Vol. 170. EPJ web of conferences. Les Ulis Cedex A: EDP Sciences; 2018:04017 (5 pp.). https://doi.org/10.1051/epjconf/201817004017
    DORA PSI
  • Pakari O, Lamirand V, Perret G, Godat D, Hursin M, Frajtag P, et al.
    Investigation of spatial effects on neutron noise measurements in the zero power reactor CROCUS
    In: Proceedings of the PHYSOR 2018. LaGrange Park, IL, USA: American Nuclear Society; 2018:(12 pp.).
    DORA PSI
  • Papadopoulos P, Lind T, Prasser H-M
    Analyzing droplet size distributions inside a self-priming venturi scrubber for filtered containment venting systems
    In: Proceedings of the 2018 26th international conference on nuclear engineering (ICONE26). Thermal hydraulics and safety analyses. New York: American Society of Mechanical Engineers (ASME); 2018:ICONE26-82227 (7 pp.). https://doi.org/10.1115/ICONE26-82227
    DORA PSI
  • Perret G, Rahman S, Wicaksono D
    Deterministic sampling and Gaussian Process metamodel approach applied to a station black out accident model
    Presented at: ANS best estimate plus uncertainty international conference (BEPU 2018); May 13-18, 2018; Lucca, Italy.
    DORA PSI
  • Prasser H-M, Janasz F, Suckow D, Szogradi M
    Non-condensable gas plugging and mixing behavior in PWR steam generator tubes during reflux condensation
    In: Proceedings of the 26th international conference on nuclear engineering (ICONE26). Thermal hydraulics and safety analyses. New York: American Society of Mechanical Engineers (ASME); 2018:ICONE26-82350 (10 pp.). https://doi.org/10.1115/ICONE26-82350
    DORA PSI
  • Puragliesi R, Mukin R, Clifford I, Ferroukhi H, Seidl M
    Computational fluid dynamics as a tool for deriving subchannel model parameters - The PSBT case study
    In: Proceedings of the 26th international conference on nuclear engineering (ICONE26). Computational fluid dynamics (CFD); nuclear education and public acceptance. Vol. 8. New York: American Society of Mechanical Engineers (ASME); 2018:ICONE26-81743 (13 pp.). https://doi.org/10.1115/ICONE26-81743
    DORA PSI
  • Rochman D, Vasiliev A, Ferroukhi H, Janin D, Seidl M
    Best estimate plus uncertainty analysis for the 244CM prediction in spent fuel characterization
    Presented at: ANS best estimate plus uncertainty international conference (BEPU 2018); May 13-18, 2018; Lucca, Italy.
    DORA PSI
  • Scolaro A, Clifford I, Fiorina C, Pautz A
    First steps towards the development of a 3D nuclear fuel behaviour solver with OpenFOAM
    In: Proceedings of the 26th international conference on nuclear engineering (ICONE26). Nuclear fuel and material, reactor physics, and transport theory. Vol. 3. sine loco: American Society of Mechanical Engineers (ASME); 2018:ICONE26-82381 (10 pp.). https://doi.org/10.1115/ICONE26-82381
    DORA PSI
  • Siefman D, Hursin M, Aufiero M, Bidaud A, Pautz A
    Convergence analysis and criterion for data assimilation with sensitivities from Monte Carlo neutron transport codes
    In: Proceedings of the PHYSOR 2018. LaGrange Park, IL, USA: American Nuclear Society; 2018:(10 pp.).
    DORA PSI
  • Sublet J-C, Koning A, Rochman D
    TENDL-2017: the making of multi-faceted technological nuclear data library
    In: Radiation protection and shielding division 20th topical meeting. Illinois: American Nuclear Society (ANS); 2018:(7 pp.).
    DORA PSI
  • Tambouratzis T, Chionis D, Dokhane A
    General regression neural networks for the concurrent, timely and reliable identification of detector malfunctions and/or nuclear reactor deviations from steady-state operation
    In: Sundaram S, ed. Proceedings of the 2018 IEEE symposium series on computational intelligence (SSCI 2018). Piscataway: IEEE; 2018:524-531. https://doi.org/10.1109/SSCI.2018.8628700
    DORA PSI
  • Vitullo F, Krepel J, Kalilainen J, Prasser H-M, Pautz A
    Statistical burnup distribution of moving pebbles in HTR-PM reactor
    In: Proceedings of the 26th international conference on nuclear engineering (ICONE26). Student Paper Competition. New York: American Society of Mechanical Engineers (ASME); 2018:ICONE26-81082 (10 pp.). https://doi.org/10.1115/ICONE26-81082
    DORA PSI


Impact of Nuclear Data Uncertainty in the Modeling of Recoil Atom Energy Distributions in Silicon
P.J. Griffin, A. Koning, D. Rochman
ANS RPSD 2018, 20th Topical Meeting of the Radiation Protection & Shielding Division of ANS Santa Fe, NM, August 26 31, 2018


Effect of Nuclear Data on the DNBR Preduction with Subchannel code COBRA-TF
R. Mukin, D. Rochman, I. Clifford, A. Vasiliev, H. Ferrouhki
BEPU 2018: Best Estimate Plus Uncertainty International Conference Lucca, Italy, May 13-18, 2018



Global Sensitivity Analysis and Registration Strategy for Temperature Profiles of Reflood Experiment Simulations
G. Perret, D. Wicaksono
BEPU 2018: Best Estimate Plus Uncertainty International Conference Lucca, Italy, May 13-18, 2018


Criticality Safety Evaluations for the concept of Swiss PWR Soent Fuel Geological Repository
A. Vasiliev, J. Herrero, D. Rochman, M. Pecchia, H. Ferroukhi, S. Caruso
BEPU 2018: Best Estimate Plus Uncertainty International Conference Lucca, Italy, May 13-18, 2018


Representativity Analysis of the LWR-PROTEUS Phase II Experiments Using SHARKX Stochastic Sampling Method
M. Hursin, D. Siefman, G. Perret, A. Pautz
BEPU 2018: Best Estimate Plus Uncertainty International Conference Lucca, Italy, May 13-18, 2018


The Importance of Experimental Uncertainty in the BEPU Approach
M. Hursin
BEPU 2018: Best Estimate Plus Uncertainty International Conference Lucca, Italy, May 13-18, 2018


Studies Of Intra-Pin Power Distributions In Operated Bwr Fuel Assemblies Using Mcnp With A Cycle Check-Up Methodology
M. Pecchia, H. Ferroukhi, A. Vasiliev, P. Grimm
Physor 2018: Reactor Physics Paving The Way Towards More Efficient Systems Cancun, Mexico, April 22-26, 2018


Studies On The Effects Of Local Power Peaking On Heat Transfer Under Dryout Conditions In Bwrs
I.Clifford, M. Pecchia, R. Mukin, H. Ferroukhi, A. Gorzel
Physor 2018: Reactor Physics Paving The Way Towards More Efficient Systems Cancun, Mexico, April 22-26, 2018


Towards Systematic And Continuous Tracking Of Neutron And Process Noise Signatures During Lwr Operation
A. Dokhane, D. Chionis, H. Ferroukhi
Physor 2018: Reactor Physics Paving The Way Towards More Efficient Systems Cancun, Mexico, April 22-26, 2018

On The Importance Of The Neutron Scattering Angular Distributions For The Lwr Fast Neutron Dosimetry
A. Vasiliev, D. Rochman, M. Pecchia, H. Ferroukhi
Physor 2018: Reactor Physics Paving The Way Towards More Efficient Systems Cancun, Mexico, April 22-26, 2018

Optimization And Sensitivity Studies Towards Pwr Structures Activation Characterization Using The Mcnp Code
B. Jung, A. Vasiliev, M. Pecchia, H. Ferroukhi
Ans Student Conference 2018, University of Florida, Gainesville Fl, Usa, April 5 - 7 2018,

 

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