Open Access
Issue
EPJ Nuclear Sci. Technol.
Volume 2, 2016
Article Number 32
Number of page(s) 16
DOI https://doi.org/10.1051/epjn/2016025
Published online 23 August 2016
  1. IAEA, Fission product nuclear data, Technical document IAEA-213, 1977 [Google Scholar]
  2. OECD, Fission product nuclear data, Technical document NEA/NSC/DOC(92)9, 1992 [Google Scholar]
  3. M.B. Chadwick et al., ENDF/B-VII.1 nuclear data for science and technology: cross sections, covariances, fission product yields and decay data, Nucl. Data Sheets 112, 2887 (2011) [CrossRef] [Google Scholar]
  4. K. Shibata et al., JENDL-4.0: a new library for nuclear science and engineering, J. Nucl. Sci. Technol. 48, 1 (2011) [Google Scholar]
  5. M.A. Kellett et al., The JEFF-3.1/-3.1.1 radioactive decay data and fission yields sub-libraries, Technical document, JEFF report 20, 2009 [Google Scholar]
  6. G. Rimpault et al., The ERANOS code and data system for fast reactor neutronic analyses, in Proc. Int. Conf. PHYSOR 2002, Seoul, Korea (2002) [Google Scholar]
  7. J.M. Ruggieri et al., ERANOS 2.1: the international code system for GEN-IV fast reactor analysis, in Proc. Int. Congress on Advances in Nuclear Power Plants, ICAPP06, Reno, USA (2006) [Google Scholar]
  8. J. Tommasi et al., Analysis of sample irradiation experiments in PHENIX for JEFF-3.0 nuclear data validation, Nucl. Sci. Eng. 154, 119 (2006) [Google Scholar]
  9. J. Tommasi et al., Analysis of the PROFIL and PROFIL-2 sample irradiation experiments in PHENIX for JEFF-3.1 nuclear data validation, Nucl. Sci. Eng. 160, 232 (2008) [Google Scholar]
  10. A. Santamarina et al., The JEFF-3.1.1 Nuclear Data Library, Technical document, JEFF report 22, 2009 [Google Scholar]
  11. A. Gandini, J. Nucl. Energy 21, 755 (1967) [CrossRef] [Google Scholar]
  12. K.-H. Schmidt et al., General Description of Fission Observables, JEFF Report 24, NEA Data Bank, 2014 [Google Scholar]
  13. K.-H. Schmidt et al., General description of fission observables: GEF model code, Nucl. Data Sheets 131, 107 (2016) [CrossRef] [Google Scholar]
  14. R.W. Mills, Fission product yield evaluation, PhD thesis, University of Birmingham, 1995 [Google Scholar]
  15. A.R. Date, A.L. Gray, Analyst 108, 159 (1983) [CrossRef] [Google Scholar]
  16. E. Privas et al., The use of nuclear data as Nuisance parameters in the integral data assimilation of the PROFIL experiments, Nucl. Sci. Eng. 182, 377 (2016) [Google Scholar]
  17. A.D. Carlson et al., International evaluation of neutron cross section standards, Nucl. Data Sheets 110, 3215 (2009) [CrossRef] [Google Scholar]
  18. J. Tommasi, private communication, 2007 [Google Scholar]
  19. Z.Y. Bao et al., Neutron cross sections for nucleosynthesis studies, At. Data Nucl. Data Tables 76, 70 (2000) [Google Scholar]
  20. S.F. Mughabghab, Atlas of Neutron Resonances , 5th ed. (Elsevier, Amsterdam, 2006) [Google Scholar]
  21. P. Archier et al., CONRAD evaluation code: development status and perspectives, Nucl. Data Sheets 118, 488 (2014) [CrossRef] [Google Scholar]
  22. W. Davies, Absolute measurements of fission yields for 235U and 239Pu in the Dounreay fast reactor, Radio. Acta 12, 174 (1969) [Google Scholar]
  23. F.L. Lisman et al., Fission yields of over 40 stable and long-lived fission products for thermal neutron fissioned 233U, 235U, 239Pu and 241Pu and fast reactor fissioned 235U and 239Pu, Nucl. Sci. Eng. 42, 191 (1970) [CrossRef] [Google Scholar]
  24. M. Robin et al., The importance of fission product nuclear data in burnup determination, in Proc. Int. Conf. on Chemical and Nuclear Data, Canterbury, UK (1973) [Google Scholar]
  25. L. Koch, Systematics of fast cumulative fission yields, Radio. Acta 29, 61 (1981) [Google Scholar]
  26. W.J. Maeck, Fast reactor fission yields for 233U, 235U, 238U and 239Pu, and recommendations for the determination of burnup on FBR mixed oxide fuels, in Proc. Int. Conf. on Nuclear Cross Sections and Technology, Washington, USA (1975) [Google Scholar]
  27. M. Rajagopalan et al., Mass yields in the fission of Uranium-235 and Plutonium-239 in the neutron spectrum of a gas-cooled fast reactor, Nucl. Sci. Eng. 58, 414 (1975) [CrossRef] [Google Scholar]
  28. W.J. Maeck et al., Revised EBR-II fast-reactor fission yields for 233U, 235U and 238U, Exxon Nuclear Idaho Company, report ENICO-1091, 1981 [Google Scholar]

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