Keywords:Nuclear Transmutation, Ruthenium, Thermal Neutron Capture Cross Section, MVP-BURN, ORLIBJ40
We have been studying creation of element resources by nuclear transmutation of fission products (FP), performing both computational simulation and nuclear reactor experiments. In the previous presentation, we had pointed out that the thermal neutron capture cross section of 102Ru in JENDL-4.0 could have been overestimated approximately 20%, based on the result of an integral experiment had been done by ourselves. Changing the evaluated value of 102Ru (1.475 b) to an estimated value based on the experiment (1.204 b) would affect on some conventional simulated quantities such as production amounts and transmutation characteristics of FP. In this presentation, we will show such effects analyzed by using burnup calculation codes; MVP-BURN and ORLIBJ40.