Re-evaluation of nuclear data of fission product nuclides for JENDL-3.2

Re-evaluation was performed for the neutron-induced reaction data of fissio n product nuclides compiled in the Japanese Evaluated Nuclear Data Library, JENDL-3.1. The nuclides whose data were re-evaluated are 63 nuclides from As-75 to Eu-155. Main quantities revised are the resonance parameters, capt ure cross sections and inelastic scattering cross sections. As the results of re-evaluation, the thermal neutron capture cross sections, the resonance integrals and the capture cross sections in the keV region were largely im proved. The evaluated data cover the neutron energy region from 10(-5) eV t o 20 MeV. The present results have been adopted to JENDL-3.2.