Community Research and Development Information Service - CORDIS

Abstract

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.

Additional information

Authors: MALHERBE J, CEA, Département de l'Industrialisation des Procédés, Fontenay-aux-Roses (FR);DALLE C, CEA, Département de l'Industrialisation des Procédés, Fontenay-aux-Roses (FR);LAIZIER J ET AL., CEA, Département de l'Industrialisation des Procédés, Fontenay-aux-Roses (FR)
Bibliographic Reference: EUR 13082 EN (1990) 47 pp., FS, ECU 5
Availability: (2)
ISBN: ISBN 92-826-1897-8
Record Number: 199011846 / Last updated on: 1994-12-02
Category: PUBLICATION
Original language: en
Available languages: en