| Issue |
EPJ Nuclear Sci. Technol.
Volume 11, 2025
Special Issue on ‘Overview of recent advances in HPC simulation methods for nuclear applications’, edited by Andrea Zoia, Elie Saikali, Cheikh Diop and Cyrille de Saint Jean
|
|
|---|---|---|
| Article Number | 54 | |
| Number of page(s) | 10 | |
| DOI | https://doi.org/10.1051/epjn/2025049 | |
| Published online | 12 September 2025 | |
- F. Courtin, C. Laguerre, P. Miranda, C. Chabert, G. Martin, Pu multi-recycling scenarios towards a PWR fleet for a stabilization of spent fuel inventories in France, EPJ Nuclear Sci. Technol. 7, 23 (2021) https://doi.org/10.1051/epjn/2021022 [Google Scholar]
- A. Eustache, G. Martin, C. Chabert, F. Sudreau, C. Evans, F. Laugier, G. Vaast, B. Carlier, O. Tougait, Simulation of the performances of a Pressurized Water Reactors multi-recycling nuclear system for material valorization, Prog. Nucl. Sci. Technol. 7, (2025) [Google Scholar]
- G. Krivtchik, COSI7: The new CEA reference electro-nuclear simulation tool, EPJ Web Conf. 247, 13001 (2021) [CrossRef] [EDP Sciences] [Google Scholar]
- N. Thiollière et al. A methodology for performing sensitivity analysis in dynamic fuel cycle simulation studies applied to a PWR fleet simulated with the CLASS tool, EPJ Nuclear Sci. Technol. 4, 13 (2018) [Google Scholar]
- EDF, UK EPR - Generic Design Assessment (GDA), 09 07 2023. Available: https://www.edfenergy.com/energy/nuclear-new-build-projects/hinkley-point-c/reactor/uk-epr-generic-design-assessment [Google Scholar]
- A. Santamarina, D. Bernard, P. Blaise, P. Leconte, R. Le Tellier, C. Vaglio-Gaudard, J.-F. Vidal, in Apollo2.8: A validated code package for pwr neutronics calculations (2009), Vol. 2, pp. 04 [Google Scholar]
- J. Lautard, C. Magnaud, F. Moreau, A. Baudron, Cronos 2: a neutronic simulation software for reactor core calculations, CEA-R-5889, CEA/Saclay, Direction des Reacteurs Nucleaires (DRN), 1999 [Google Scholar]
- A. Santamarina et al., The JEFF-3.1. 1 nuclear data library, JEFF Rep. 22, 2 (2009) [Google Scholar]
- S. Eveillard, F. Courtin, X. Doligez, M. Ernoult, N. Thiollière, K. Tirel, J.F. Vidal, Sensitivity studies of pwr mox fuel management to the plutonium initial vector using artificial neural networks, EPJ Web Conf. 302, 17008 (2024). Available: https://doi.org/10.1051/epjconf/202430217008 [Google Scholar]
- J.F. Vidal, O. Litaize, R. Tran, D. Bernard, A. Santamarina, C. Vaglio-Gaudard, New modelling of LWR assemblies using the apollo2 code package, M&C SNA Mathematics and Computation and Supercomputing in Nuclear Applications, 2007 [Google Scholar]
- B. Leniau et al., A neural network approach for burn-up calculation and its application to the dynamic fuel cycle code CLASS, Ann. Nucl. Energy, 81, 125 2015. [CrossRef] [Google Scholar]
- G. Krivtchik, P. Blaise, C. Coquelet-Pascal, Artificial neural network surrogate development of equivalence models for nuclear data uncertainty propagation in scenario studies, EPJ Nuclear Sci. Technol. 3, 22 (2017) [Google Scholar]
- A. Hoecker et al., TMVA: Toolkit for Multivariate Data Analysis, ACAT, S, 2007 [Google Scholar]
- S. Eveillard, F. Courtin, X. Doligez, M. Ernoult, N. Thiollière, K. Tirel, J.-F. Vidal, Impact of fuel loading models on fuel cycle dynamic simulations, Prog. Nucl. Sci. Technol., 7, (2025) [Google Scholar]
- K. Kosowski, M. Seidl, Operation cycle length extension of a KONVOI PWR - requirements and experience from operator's viewpoint, in The 19 th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-19), Belgium (2022) [Google Scholar]
Current usage metrics show cumulative count of Article Views (full-text article views including HTML views, PDF and ePub downloads, according to the available data) and Abstracts Views on Vision4Press platform.
Data correspond to usage on the plateform after 2015. The current usage metrics is available 48-96 hours after online publication and is updated daily on week days.
Initial download of the metrics may take a while.
