Plutonium and Minor Actinides Utilization in FUJI-U1 Molten Salt Reactor

Abstract

One type of standard Molten Salt Reactor (MSR) uses graphite as moderator and LiF-BeF2-ThF4-233UF4 as fuel. Recycling of spent nuclear such as plutonium and minor actinides are considered as one of the effective ways to handle the spent nuclear fuel. Plutonium and minor actinides utilization in FUJI-U1 type of MSR have been evaluated. MSR FUJI U1 is one of small MSR which was designed by Japan. Neutronic calculation was performed using PIJ modules of SRAC 2006 code with JENDL 4.0 as nuclear data library. Several neutronic parameters, such as effective multiplication factor, conversion ratio, and neutron spectrum were evaluated. Even though there are several types of plutonium, in this study, only reactor grade plutonium was taken into account.