フォロー
Mathieu Hursin
タイトル
引用先
引用先
The joint evaluated fission and fusion nuclear data library, JEFF-3.3
AJM Plompen, O Cabellos, C De Saint Jean, M Fleming, A Algora, ...
The European Physical Journal A 56, 1-108, 2020
6812020
A collision history-based approach to sensitivity/perturbation calculations in the continuous energy Monte Carlo code SERPENT
M Aufiero, A Bidaud, M Hursin, J Leppänen, G Palmiotti, S Pelloni, ...
Annals of Nuclear Energy 85, 245-258, 2015
1722015
Nuclear data uncertainties for typical LWR fuel assemblies and a simple reactor core
D Rochman, O Leray, M Hursin, H Ferroukhi, A Vasiliev, A Aures, ...
Nuclear Data Sheets 139, 1-76, 2017
632017
Extension of the GeN-Foam neutronic solver to SP3 analysis and application to the CROCUS experimental reactor
C Fiorina, M Hursin, A Pautz
Annals of Nuclear Energy 101, 419-428, 2017
602017
Overview of the CORTEX project
C Demazière, P Vinai, M Hursin, S Kollias, J Herb
Proceedings of PHYSOR 2018, 2971-2980, 2018
562018
Nuclear data uncertainty propagation on spent fuel nuclide compositions
O Leray, D Rochman, P Grimm, H Ferroukhi, A Vasiliev, M Hursin, ...
Annals of Nuclear Energy 94, 603-611, 2016
532016
Full core, heterogeneous, time dependent neutron transport calculations with the 3D code DeCART
M Hursin
University of California, Berkeley, 2010
442010
Methodology for core analyses with nuclear data uncertainty quantification and application to Swiss PWR operated cycles
O Leray, H Ferroukhi, M Hursin, A Vasiliev, D Rochman
Annals of Nuclear Energy 110, 547-559, 2017
392017
Benchmarking and application of the state-of-the-art uncertainty analysis methods XSUSA and SHARK-X
A Aures, F Bostelmann, M Hursin, O Leray
Annals of Nuclear Energy 101, 262-269, 2017
322017
Synergism of the method of characteristic, R-functions and diffusion solution for accurate representation of 3D neutron interactions in research reactors using the AGENT code …
M Hursin, S Xiao, T Jevremovic
Annals of Nuclear Energy 33 (13), 1116-1133, 2006
322006
Future experimental programmes in the CROCUS reactor
VP Lamirand, M Hursin, G Perret, P Frajtag, O Pakari, A Pautz
Conference proceedings of RRFM/IGORR 2016, 284-292, 2016
292016
Coupled computational fluid dynamics and MOC neutronic simulations of Westinghouse PWR fuel assemblies with grid spacers
J Yan, B Kochunas, M Hursin, T Downar, Z Karoutas, E Baglietto
292011
Stochastic vs. sensitivity-based integral parameter and nuclear data adjustments
D Siefman, M Hursin, D Rochman, S Pelloni, A Pautz
The European Physical Journal Plus 133 (10), 429, 2018
262018
Full Core modeling techniques for research reactors with irregular geometries using Serpent and PARCS applied to the CROCUS reactor
DJ Siefman, G Girardin, A Rais, A Pautz, M Hursin
Annals of Nuclear Energy 85, 434-443, 2015
252015
The Development and Implementation of a One-Dimensional Sn Method in the 2D-1D Integral Transport Solution
M Hursin, B Collins, Y Xu, T Downar
Nuclear Science and Engineering 176 (2), 186-200, 2014
252014
Neutron noise experiments in the AKR-2 and CROCUS reactors for the European project CORTEX
V Lamirand, A Rais, S Hübner, C Lange, J Pohlus, U Paquee, C Pohl, ...
EPJ Web of Conferences 225, 04023, 2020
242020
Analysis of the core power response during a PWR rod ejection transient using the PARCS nodal code and the DeCART MOC code
M Hursin, TJ Downar, B Kochunas
Nuclear science and engineering 170 (2), 151-167, 2012
232012
Iterative Bayesian Monte Carlo for nuclear data evaluation
E Alhassan, D Rochman, A Vasiliev, M Hursin, AJ Koning, H Ferroukhi
Nuclear Science and Techniques 33 (4), 50, 2022
222022
Uncertainty quantification of spent fuel nuclide compositions due to cross sections, decay constants and fission yields
O Leray, P Grimm, M Hursin, H Ferroukhi, A Pautz
202015
Comparison of Serpent and CASMO-5M for pressurized water reactors models
M Hursin, A Vasiliev, H Ferroukhi, A Pautz
International Conference on Mathematics and Computational Methods Applied to …, 2013
202013
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