Open Access
Issue
EPJ Web of Conferences
Volume 42, 2013
WONDER-2012 – 3rd International Workshop On Nuclear Data Evaluation for Reactor applications
Article Number 03001
Number of page(s) 7
Section Uncertainties and Covariance Matrices
DOI https://doi.org/10.1051/epjconf/20134203001
Published online 18 March 2013
  1. A. Santamarina, “Burnup Credit implementation in spent fuel management”, FJSS’98, CEA Cadarache, France, Augustus, 17–26 (1998) [Google Scholar]
  2. B. Roque, A. Santamarina, “Burnup Credit in LWR-MOX assemblies”, Proc. Int. Conf. on Nuclear Criticality Safety ICNC’99, Vol 4 p1666, Versailles, France, September 20-24 (1999) [Google Scholar]
  3. A. Barreau, B. Roque, A. Santamarina, C. Venard, “Recent advances in French validation program and derivation of the acceptance criteria”, Technical Meeting on Advances in Applications of Burnup Credit, IAEA-TECDOC-CD-1547, London, August 29-Sept 2 (2005) [Google Scholar]
  4. A. Santamarina & al., “Experimental validation of Burnup Credit calculation by Reactivity Worth Measurements in MINERVE Reactor”, Proc. Int. Conf. on Nuclear Criticality Safety (ICNC’95), Albuquerque, New Mexico, USA, September 17-21 (1995) [Google Scholar]
  5. A. Santamarina, N. Thiollay, C. Heulin, J.P. Chauvin, “The French Experimental Programme on Burnup Credit”, Proc. Top. Meeting on Criticality Safety Challenges, Chelan (WA), USA, September 7-11 (1997) [Google Scholar]
  6. L. San Felice & al., “Experimental validation of the DARWIN-2.3 package for fuel cycle applications”, Proc. Int. Conf. (PHYSOR 2012), Knoxville, USA, April 15-20, 2012 [Google Scholar]
  7. J.M Gomit & al., “CRISTAL Criticality package : twelve years later and new features”, Proc. Int. Conf. on Nuclear Criticality Safety (ICNC 2011), Edinburgh, UK, September 19-22 (2011) [Google Scholar]
  8. A. Santamarina & al., “The JEFF-3.1.1 Nuclear Data Library,” JEFF Report 22, OECD 2009, NEA No.6807 [Google Scholar]
  9. A. Gruel, P. Leconte, D. Bernard, P. Archier, G. Noguère, “Interpretation of Fission Product Oscillations in the MINERVE reactor, from Thermal to Epithermal Spectra”, Nucl. Sci. and Eng, 169, 229–224 (2011) [Google Scholar]
  10. A. Santamarina, D. Bernard, P. Blaise, L. Erradi, R. Letellier, C. Vaglio, J-F. Vidal, “APOLLO2.8 : a validated code package for PWR calculations,” Proc. Int. Conf. Advances in Nuclear Fuel Management ANFM-IV, Hilton Head Island (SC), USA, April 12-15 (2009). [Google Scholar]
  11. C. Venard, A. Santamarina, A. Leclainche, C. Mounier, “The RIB tool for the determination of computational bias and associated uncertainty in the CRISTAL criticality-safety package”, Proc. Int. Conf. NCSD 2009, Shilo Inn, Richland, Washington, USA, September 13-17 (2009) [Google Scholar]
  12. A. Santamarina, D. Bernard, N. Dos Santos, O. Leray, C. Vaglio, L. Leal, “Re-estimation of Nuclear Data and JEFF-3.1.1 uncertainty calculation”, Proc. Int. Conf. PHYSOR 2012, Knoxville, USA, April 15-20 (2012) [Google Scholar]
  13. De Saint Jean, P. Archier, G. Noguere, O. Litaize, C. Vaglio, D. Bernard, O. Leray, “Estimation of multi-group cross section covariances of 238,235 U, 239Pu, 241Am, 56Fe and 23Na”, Proc. Int. Conf. PHYSOR 2012, Knoxville, USA, April 15-20 (2012) [Google Scholar]