IMPACT OF FISSION PRODUCTS IMPURITY ON THE PLUTONIUM CONTENT IN PWR MOX FUELS

Youinou, Gilles ; Alfonsi, Andrea

Idaho National Laboratory

关键词: Reprocessing;    Spent Fuels Fission Products Impurity;    Plutonium;    Pwr Type Reactors;    11 Nuclear Fuel Cycle And Fuel Materials;   

DOI  :  10.2172/1048410
RP-ID  :  INL/EXT-12-26114
RP-ID  :  DE-AC07-05ID14517
RP-ID  :  1048410

美国|英语

来源: UNT Digital Library

【 摘 要 】

This report presents the results of a neutronics analysis done in response to the charter IFCA-SAT-2 entitled 'Fuel impurity physics calculations'. This charter specifies that the separation of the fission products (FP) during the reprocessing of UOX spent nuclear fuel assemblies (UOX SNF) is not perfect and that, consequently, a certain amount of FP goes into the Pu stream used to fabricate PWR MOX fuel assemblies. Only non-gaseous FP have been considered (see the list of 176 isotopes considered in the calculations in Appendix 1). This mixture of Pu and FP is called PuFP. Note that, in this preliminary analysis, the FP losses are considered element-independent, i.e., for example, 1% of FP losses mean that 1% of all non-gaseous FP leak into the Pu stream.