Multirecycling of Plutonium from LMFBR Blanket in Standard PWRs Loaded with MOX Fuel

Sen, Sonat ; Youinou, Gilles

Idaho National Laboratory

关键词: Mox;    Pwr;    Multirecycling;    22 General Studies Of Nuclear Reactors Mox;   

DOI  :  10.2172/1082390
RP-ID  :  INL/EXT-13-28448
RP-ID  :  DE-AC07-05ID14517
RP-ID  :  1082390

美国|英语

来源: UNT Digital Library

【 摘 要 】

It is now well-known that, from a physics standpoint, Pu, or even TRU (i.e. Pu+M.A.), originating from LEU fuel irradiated in PWRs can be multirecycled also in PWRs using MOX fuel. However, the degradation of the isotopic composition during irradiation necessitates using enriched U in conjunction with the MOX fuel either homogeneously or heterogeneously to maintain the Pu (or TRU) content at a level allowing safe operation of the reactor, i.e. below about 10%. The study is related to another possible utilization of the excess Pu produced in the blanket of a LMFBR, namely in a PWR(MOX). In this case the more Pu is bred in the LMFBR, the more PWR(MOX) it can sustain. The important difference between the Pu coming from the blanket of a LMFBR and that coming from a PWR(LEU) is its isotopic composition. The first one contains about 95% of fissile isotopes whereas the second one contains only about 65% of fissile isotopes. As it will be shown later, this difference allows the PWR fed by Pu from the LMFBR blanket to operate with natural U instead of enriched U when it is fed by Pu from PWR(LEU)