軽水炉体系における照射後試験解析による新たに評価された核分裂収率の妥当性確認

抄録

Fission yield is an important physical quantity used to evaluate the amount of fission products after irradiation. The fission yield used in Japanese Evaluated Nuclear Data Library (JENDL) employs ENDF/B data for many nuclides. On the other hand, the fission yield has recently been evaluated in Japan on the basis of various theories. As one of the evaluations, the fission yield has been newly evaluated by a team from Tokyo Institute of Technology (Tokyo Tech). It is necessary to confirm the validity of the fission yield evaluated by Tokyo Tech because the fission yield is used as the sublibrary of JENDL-5. In this study, the analysis of the post-irradiation examination results of UO₂ fuel and MOX fuel was performed for the validation of the fission yield evaluated by Tokyo Tech, and the result is compared with that of JENDL FP Fission Yields Data File 2011 (FPY-2011). Using the integrated burnup calculation code system SWAT4.0, the results of the post-irradiation examinations of Fukushima-Daini-2 and Beznau-1 were analyzed. The difference in the production of fission products observed from the fission yields evaluated by Tokyo Tech and those by FPY-2011 is about 5% at maximum.