Nuclear data for nuclear fuel cycle. Current status and problems

Concerning the evaluation of U-Pu nuclear fuel cycle, especially the present status of the nuclear data on other minor actinides than major U and Pu and their roles are reviewed, and the problems are pointed out. By the recent measurement, though the remarkable improvement of both quality and quantity of the evaluated values has been observed, when one group cross sections in JENDL-3 and ORIGEN 2/82 libraries are compared, considerable difference is found. Further, the evaluation of the amount of nuclide formation in spent fuel and the problems in the application to the calculation of the irradiation extinction of transuranium elements are discussed. In the autumn of 1989, JENDL-3, the third edition of Japanese evaluated nuclear data library, was completed. In this file, on 324 nuclides, the nuclear data of all reactions at neutron energy of 0-20 MeV are contained. The present status of such nuclear data as nuclear fission cross section, capture cross section, (n, 2n) reaction cross section and others, the nuclear data on the decay of actinides and radioactivity, the one group cross section for burning calculation, the comparison of the measured values and the calculated values in burning and so on are reported. (K.I.)