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Ce contenu n'est pas disponible en français.Conference Articles
2018
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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. https://doi.org/10.1115/ICONE26-82360
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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.
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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. https://doi.org/10.1051/epjconf/201817803004
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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.
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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.
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Cozzo C, Khvostov G
ATF developments in FALCON V1 at PSI
In: Topfuel 2018. Part 4. Brussels: European Nuclear Society; 2018.
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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. https://doi.org/10.1109/SSCI.2018.8628637
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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.
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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.
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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.
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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.
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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.
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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.
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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. https://doi.org/10.1109/NSSMIC.2018.8824470
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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. https://doi.org/10.1520/STP160820170090
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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.
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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. https://doi.org/10.1115/ICONE26-81749
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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. https://doi.org/10.1115/ICONE26-82546
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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.
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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.
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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. https://doi.org/10.1115/ICONE26-82227
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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.
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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. 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. https://doi.org/10.1115/ICONE26-81743
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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.
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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. 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.
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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.
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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. https://doi.org/10.1109/SSCI.2018.8628700
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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. 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,