Characteristics and management of waste produced by the MOX fuel cycle in light-water reactors
Mixed UO(2) - PuO(2), called "MOX", should gradually be introduced into the light-water reactor fuel cycle. It offers a rational use of the plutonium made available after reprocessing. This study compares the waste produced by the manufacture and reprocessing after irradiation of MOX fuels with that produced by the UOX cycle (235U enriched uranium oxide). The presence of larger quantities of actinides in the MOX fuel requires the verification of the behaviour of waste encapsulation under alpha irradiation beyond current specifications. The reprocessing of the MOX by dilution in standard UOX fuels means that the majority of the specifications can be complied with without modifying the volume of waste.
Bibliographic Reference: EUR 13082 EN (1990) 47 pp., FS, ECU 5
ISBN: ISBN 92-826-1897-8
Record Number: 199011846 / Last updated on: 1994-12-02
Original language: en
Available languages: en