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[en] The reliability of critical safety evaluation of MOX fuel management is determined by 239Pu and 238U neutron data accuracy. A qualitative analysis of up-to-date knowledge on these data, important for nuclear safety assurance, is given in the paper. The analysis of existing experimental information shows a need for additional integral benchmark experiments for low-moderated MOX media. Experiments performed and planned at the BFS facility might provide valuable information on the quality of nuclear data. (author)
Source
Organisation for Economic Co-Operation and Development - Nuclear Energy Agency, 75 - Paris (France); 219 p; ISBN 92-64-02078-0; 
; 2004; p. 99-111; Workshop of the OECD/NEA Nuclear Science Committee; Paris (France); 14-15 Apr 2004
; 2004; p. 99-111; Workshop of the OECD/NEA Nuclear Science Committee; Paris (France); 14-15 Apr 2004