Open Access
EPJ Nuclear Sci. Technol.
Volume 7, 2021
Article Number 17
Number of page(s) 26
Published online 22 October 2021
  1. F. Varaine, Ph. Marsault, M.-S. Chenaud et al., Pre-conceptual design study of ASTRID core, in Proceedings of the 2012 International Congress on Advances in Nuclear Power Plants-ICAPP'12 (2012) [Google Scholar]
  2. G. Rimpault, The ERANOS data and code system for fast reactor neutronic analyses, in Proc. Int. Conf. PHYSOR, Seoul, South Korea, Oct. 7–10, 2002 (2002) [Google Scholar]
  3. D. Schneider et al., APOLLO3: CEA/DEN deterministic multi-purpose code for reactor physics analysis, in Proc. PHYSOR 2016 (2016), pp. 1–5 [Google Scholar]
  4. E. Brun, F. Damian, C.M. Diop, E. Dumonteil, F.X. Hugot, C. Jouanne et al., TRIPOLI-4®, CEA, EDF and AREVA reference Monte Carlo code, in SNA+ MC 2013-Joint International Conference on Supercomputing in Nuclear Applications+ Monte Carlo (p. 06023). EDP Sciences (2014) [Google Scholar]
  5. T.H. Fanning, Sodium as a fast reactor coolant, in Topical seminar series on sodium fast reactors, Argonne National Laboratory, Lemont, IL (2007), pp. 1–50 [Google Scholar]
  6. P. Sciora, L. Buiron, G. Rimpault, F. Varaine, A break even oxide fuel core for an innovative SFR: CEA neutronic studies (2009) [Google Scholar]
  7. A. Santamarina, D. Bernard, P. Blaise, M. Coste, A. Courcelle, T.D. Huynh, C. Jouanne, P. Leconte, O. Litaize, S. Mengelle et al., The JEFF-3.1.1 nuclear data library, JEFF report 22, 2 (2009) [Google Scholar]
  8. E. Sartori, Standard energy group structures of cross section libraries for reactor shielding, reactor cell and fusion neutronics applications: VITAMIN-J, ECCO-33, ECCO-2000 and XMAS. JEF/DOC-315, Revision, 3 (1990) [Google Scholar]
  9. C.B. Carrico, E.E. Lewis, G. Palmiotti, Three-dimensional variational nodal transport methods for cartesian, triangular, and hexagonal criticality calculations, Nucl. Sci. Eng. 111, 168–179 (1992) [CrossRef] [Google Scholar]
  10. A. Hajji, C. Coquelet-Pascal, P. Blaise, Deterministic and Monte-Carlo interpretations of the MASURCA/BALZAC-SI internal storage SFR experiment and quantification of uncertainties to nuclear data, Ann. Nucl. Energy 154, 108098 (2021) [CrossRef] [Google Scholar]
  11. A. Hajji, C. Coquelet-Pascal, P. Blaise, Interpretation of the ASPIS Iron 88 programme with TRIPOLI-4 and quantification of uncertainties due to nuclear data, Ann. Nucl. Energy 140, 107147 (2020) [CrossRef] [Google Scholar]
  12. A. Hajji C. Coquelet-Pascal, P. Blaise, Interpretation of the JANUS Phase 7 shielding experiment with TRIPOLI-4 and quantification of uncertainties due to nuclear data, Ann. Nucl. Energy 149, 107797 (2020) [Google Scholar]
  13. C.E. Shannon, A mathematical theory of communication, Bell Syst. Tech. J. 27, 379–423 (1948) [CrossRef] [Google Scholar]
  14. B. Faure, P. Archier, J.F. Vidal, L. Buiron, A 2D/1D algorithm for effective cross-section generation in fast reactor neutronic transport calculations, Nucl. Sci. Eng. 192, 40–51 (2018) [CrossRef] [Google Scholar]
  15. A. Hajji, C. Coquelet-Pascal, P. Blaise, B. Faure, Neutron shielding calculations in fast reactors with APOLLO3 ®: identification of important physical phenomena. ICAPP, 2019 [Google Scholar]
  16. H. Guo, E. Garcia, B. Faure, L. Buiron, P. Archier, P. Sciora, G. Rimpault, Advanced method for neutronic simulation of control rods in sodium fast reactors: numerical and experimental validation, Ann. Nucl. Energy 129, 90–100 (2019) [CrossRef] [Google Scholar]
  17. G.H. Kinchin, R.S. Pease, The displacement of atoms in solids by radiation, Rep. Progr. Phys. 18, 1 (1955) [CrossRef] [Google Scholar]
  18. T. Beck et al., Conceptual design of ASTRID radial shielding sub-assemblies, Nucl. Eng. Des. 330, 129–137 (2018) [Google Scholar]
  19. A. Lüthi, Development and validation of gamma-heating calculational methods for plutonium-burning fast reactors (No. THESIS). EPFL, 1999 [Google Scholar]
  20. P. Archier, C. De Saint Jean, G. Noguere, O. Litaize, P. Leconte, C. Bouret, COMAC. Nuclear data covariance matrices library for reactor applications (No. JAEA-CONF–2014–003), 2015 [Google Scholar]
  21. R. Macfarlane, D.W. Muir, R.M. Boicourt, A.C. Kahler III, J.L. Conlin, The NJOY Nuclear Data Processing System, Version 2016 (No. LA-UR-17-20093). Los Alamos National Lab. (LANL), Los Alamos, NM (United States), 2017 [CrossRef] [Google Scholar]
  22. K. Shibata, O. Iwamoto, T. Nakagawa, N. Iwamoto et al., JENDL-4.0: a new library for nuclear science and engineering, J. Nucl. Sci. Technol. 48, 1–30 (2011) [CrossRef] [Google Scholar]
  23. M.B. Chadwick, M. Herman, P. Obložinský, M.E. Dunn, Y. Danon, A.C. Kahler, R. Brewer, ENDF/B-VII. 1 nuclear data for science and technology: cross sections, covariances, fission product yields and decay data, Nucl. Data Sheets 112, 2887–2996 (2011) [CrossRef] [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.