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All issues Volume 7 (2021) EPJ Nuclear Sci. Technol., 7 (2021) 17 References
Open Access
Issue
EPJ Nuclear Sci. Technol.
Volume 7, 2021
Article Number 17
Number of page(s) 26
DOI https://doi.org/10.1051/epjn/2021016
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]

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