Study on transmutation of minor actinides and fission products in a prototype fast reactor with mixed-oxide fuel

We assessed the possibility of transmuting long-lived fission products, 99Tc and 129I, and minor actinides in a prototype fast reactor with mixed-oxide (MOX) fuel. The fission products were loaded into the radial blanket and were transmuted using neutrons that leaked from the core, while minor actinides were loaded into the core and were transmuted through the fission reaction and neutron-capture reaction. The transmutation rates and quantities of nuclides transmuted were calculated. The sodium void reactivity of the reactor also was estimated for cases where the reactor had fission products and/or minor actinides. We also discuss a subcritical prototype fast reactor operated by a proton accelerator. (author)