Evaluation of Depletion and Production of Uranium, Plutonium, Transplutoniums and Fission Products in Full-Core Fuel Assemblies of Japan Power Demonstration Reactor-1

Abstract

The depletion and production amounts of U, Pu, transplutoniums and fission products in the full-core fuel assemblies of Japan Power Demonstration Reactor-1 (JPDR-1) were obtained using codes for calculating three-dimensional nuclear-thermo-hydrodynamic performance, and depletion and production amounts. The results were investigated, compared with the recovery amounts in all the reprocessed fuel assemblies. As a result, the following has been found: (1) The depletion and production amounts agree well with the recovery amounts except 240Pu, 237Np and 242mAm. (2) It is necessary to calculate the depletion and production amounts by taking account of the axial distributions of void fraction and burnup of the fuel assembly. (3) Enhancement for calculational accuracy of the depletion and production amounts calls for improvement of fission energies and systematic evaluation of neutron cross sections.