Open Access
Issue
EPJ Nuclear Sci. Technol.
Volume 2, 2016
Article Number 28
Number of page(s) 15
DOI https://doi.org/10.1051/epjn/2016020
Published online 10 June 2016
  1. J.J. Duderstadt, L.J. Hamilton, Nuclear Reactor Analysis (Wiley and Sons, New York, 1976) [Google Scholar]
  2. T. Zagar, M. Ravnik, Kerntechnik 70 , 223 (2005) [CrossRef] [Google Scholar]
  3. R.M. Gomes do Prado Souza, A.Z. Mesquita, Prog. Nucl. Energy 53 , 1126 (2011) [CrossRef] [Google Scholar]
  4. T. Bily, L. Sklenka, Ann. Nucl. Eng. 71 , 91 (2014) [CrossRef] [Google Scholar]
  5. M. Tsujiet al., Nucl. Sci. Eng. 43 , 576 (2006) [Google Scholar]
  6. A. Santamarina, Thermal effects analysis in LWR lattices - Thermal cross-section shapes and qualification through French integral experiments, IAEA TECDOC-491 (see also CEA Rapport CEA-R-6215, 2009) 1989 [Google Scholar]
  7. S. Cathalauet al., MISTRAL: an experimental program in the EOLE facility devoted to 100% MOX core physics, in Proc. Int. Conf. on Physics of Reactors, PHYSOR 1996, Mito, Japan 1996 [Google Scholar]
  8. T. Yamamotoet al., Core Physics experiment of 100% MOX core MISTRAL, in Proc. Int. Conf. on Future Nuclear Systems, Yokohama, Japan, GLOBAL’97 1997 [Google Scholar]
  9. S. Cathalauet al., First validation of neutronic lattice parameters of over moderated 100% MOX fueled PWR cores on the basis of the MISTRAL experiment, in Proc. Int. Conf. on the Physics of Nuclear Science and Technology: future Nuclear Systems, Long Island, USA 1998 [Google Scholar]
  10. P. Fougeraset al., MISTRAL-4: an experimental mockup in the EOLE facility devoted to high moderation 100% MOX core Physics, in Proc. Int. Conf on the Future Nuclear Systems, GLOBAL’99, Jackson Hole, USA 1999 [Google Scholar]
  11. K. Hibiet al., Analysis of MISTRAL and EPICURE experiments with SRAC and MVP code systems, in Proc. Int. Conf. Physics of Reactor Operation, Design and Computation, PHYSOR2000, Pittsburg, USA 2000 [Google Scholar]
  12. M. Tatsumiet al., Analysis of High Moderation PWR MOX Core MISTRAL-4 with SRAC and MVP, in Proc. Int. Conf. on Nuclear Data for Science and Technology, ND2001, Tsukuba, Japan 2001 [Google Scholar]
  13. T. Yamamotoet al., Analysis of MISTRAL Experiments with JENDL-3. 2, in Proc. Int. Conf. on Nuclear Data for Science and Technology, ND2001, Tsukuba, Japan 2001 [Google Scholar]
  14. S. Cathalauet al., Full MOX recycling in ALWR: Lessons Drawn through the MISTRAL Program, in Proc. Int. Conf. PHYSOR2002, Seoul, Korea 2002 [Google Scholar]
  15. O. Litaizeet al., Analysis of the MISTRAL experiment with APOLLO2 qualification of neutronic parameters of UOX and MOX cores, in Proc. Int. Conf. PHYSOR2002, Seoul, Korea 2002 [Google Scholar]
  16. L. Erradiet al., Nucl. Sci. Eng. 144 , 47 (2003) [CrossRef] [Google Scholar]
  17. L. Erradi, A. Santamarina, Analysis of the MISTRAL experiment on the reactivity temperature coefficient for UOX and MOX lattices using JEFF-3. 1. 1 nuclear data library, in Proc. Int. Conf. PHYSOR 2010, Advances in Reactor Physics to Power the Nuclear Renaissance, Pittsburgh, USA 2010 [Google Scholar]
  18. R. Sanchezet al., Nucl. Sci. Technol 42 , 474 (2010) [Google Scholar]
  19. B.K. Jeonet al., Nucl. Techol 191 , 1 (2015) [Google Scholar]
  20. E. Brunet al., Ann. Nucl. Energy 82 , 151 (2015) [CrossRef] [Google Scholar]
  21. A. Santamarinaet al., The JEFF-3. 1. 1 Nuclear Data Library, JEFF Report 22 2009 [Google Scholar]
  22. M.B. Chadwicket al., Nucl. Data Sheets 112 , 2887 (2011) [CrossRef] [Google Scholar]
  23. J.I. Marquez Damianet al., Ann. Nucl. Energy 65 , 280 (2014) [CrossRef] [Google Scholar]
  24. R.E. MacFarlane, New thermal neutron scattering files for ENDF/B-VI, Los Alamos National Laboratory Report 1994 [Google Scholar]
  25. R.E. MacFarlane, A.C. Kahler, Nucl. Data Sheets 111 , 2739 (2010) [CrossRef] [Google Scholar]
  26. D.E. Cullenet al., How accurately we can calculate neutrons slowing down in water ?, Laurence Livermore National Laboratory Report, UCRL-TR-220605 2006 [Google Scholar]
  27. G. Vineyard, Phys. Rev. 110 , 999 (1958) [CrossRef] [Google Scholar]
  28. M. Mattes, J. Keinert, Thermal neutron scattering data for the moderator materials in ENDF-6 format and as ACE library for MCNP codes, International Atomic Energy Agency Report INDC(NDS)-0470 2005 [Google Scholar]
  29. D.I. Page, B.C. Haywood, The Harwell scattering law program: frequency distributions of moderators, Harwell Laboratory Report AERE-R-5778 1968 [Google Scholar]
  30. P. Egelstaff, P. Schofield, Nucl. Sci. Eng. 12 , 260 (1962) [Google Scholar]
  31. G. Noguere, J-C. Sublet, Ann. Nucl. Energy 35 , 2259 (2008) [CrossRef] [Google Scholar]
  32. A. Santamarinaet al., Ann. Nucl. Energy 48 , 51 (2012) [CrossRef] [Google Scholar]
  33. C. Lampoudiset al., Eur. Phys. J. Plus 128 , 86 (2013) [CrossRef] [EDP Sciences] [Google Scholar]
  34. G. Noguereet al., Phys. Rev. C 92 , 014607 (2015) [CrossRef] [Google Scholar]
  35. G. Noguere et al. accepted for publication in Nucl. Sci. Eng. (2016). [Google Scholar]
  36. P. Archieret al., Nucl. Data Sheets 118 , 488 (2014) [CrossRef] [Google Scholar]
  37. D. Bernardet al., Pu nuclear data improvements in thermal and epithermal neutron ranges, in Proc. Int. Conf. on Nuclear Data for Science and Technology Nice, France 2007 [Google Scholar]
  38. C. De Saint Jeanet al., Co-ordinated Evaluation of Plutonium-239 in the Resonance, Region, Nuclear Energy Agency Report WPEC/DOC(2014)447 2014 [Google Scholar]

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