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)
  2. T. Zagar, M. Ravnik, Kerntechnik 70 , 223 (2005) [CrossRef]
  3. R.M. Gomes do Prado Souza, A.Z. Mesquita, Prog. Nucl. Energy 53 , 1126 (2011) [CrossRef]
  4. T. Bily, L. Sklenka, Ann. Nucl. Eng. 71 , 91 (2014) [CrossRef]
  5. M. Tsujiet al., Nucl. Sci. Eng. 43 , 576 (2006)
  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
  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
  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
  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
  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
  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
  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
  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
  14. S. Cathalauet al., Full MOX recycling in ALWR: Lessons Drawn through the MISTRAL Program, in Proc. Int. Conf. PHYSOR2002, Seoul, Korea 2002
  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
  16. L. Erradiet al., Nucl. Sci. Eng. 144 , 47 (2003) [CrossRef]
  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
  18. R. Sanchezet al., Nucl. Sci. Technol 42 , 474 (2010)
  19. B.K. Jeonet al., Nucl. Techol 191 , 1 (2015)
  20. E. Brunet al., Ann. Nucl. Energy 82 , 151 (2015) [CrossRef]
  21. A. Santamarinaet al., The JEFF-3. 1. 1 Nuclear Data Library, JEFF Report 22 2009
  22. M.B. Chadwicket al., Nucl. Data Sheets 112 , 2887 (2011) [CrossRef]
  23. J.I. Marquez Damianet al., Ann. Nucl. Energy 65 , 280 (2014) [CrossRef]
  24. R.E. MacFarlane, New thermal neutron scattering files for ENDF/B-VI, Los Alamos National Laboratory Report 1994
  25. R.E. MacFarlane, A.C. Kahler, Nucl. Data Sheets 111 , 2739 (2010) [CrossRef]
  26. D.E. Cullenet al., How accurately we can calculate neutrons slowing down in water ?, Laurence Livermore National Laboratory Report, UCRL-TR-220605 2006
  27. G. Vineyard, Phys. Rev. 110 , 999 (1958) [CrossRef]
  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
  29. D.I. Page, B.C. Haywood, The Harwell scattering law program: frequency distributions of moderators, Harwell Laboratory Report AERE-R-5778 1968
  30. P. Egelstaff, P. Schofield, Nucl. Sci. Eng. 12 , 260 (1962)
  31. G. Noguere, J-C. Sublet, Ann. Nucl. Energy 35 , 2259 (2008) [CrossRef]
  32. A. Santamarinaet al., Ann. Nucl. Energy 48 , 51 (2012) [CrossRef]
  33. C. Lampoudiset al., Eur. Phys. J. Plus 128 , 86 (2013) [CrossRef] [EDP Sciences]
  34. G. Noguereet al., Phys. Rev. C 92 , 014607 (2015) [CrossRef]
  35. G. Noguere et al. accepted for publication in Nucl. Sci. Eng. (2016).
  36. P. Archieret al., Nucl. Data Sheets 118 , 488 (2014) [CrossRef]
  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
  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

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.