Community Research and Development Information Service - CORDIS

Abstract

The European Institute for Transuranium Elements is involved in the characterisation of MOX fuel irradiated in Belgian and German commercial reactors. The purpose of the present paper is to summarise experimental results and to point out from well selected results, similarities or differences - experimentally proven or predicted - in the behaviour of MOX fuel irradiated under steady-state and transient conditions. In this work, emphasis is placed on microstructural analysis of the irradiated fuels and the distribution of Pu and fission products by means of optical microscopy, image analysis and electron probe microanalysis. In addition to this, a very extensive laboratory study of interdiffusion in the sytem UO(2)/PuO(2) provides the necessary basic data to interpret aspects of the fabrication and in-pile behaviour.

Additional information

Authors: COQUERELLE M, JRC Karlsruhe (DE);MATZKE H J, JRC Karlsruhe (DE);WALKER C T, JRC Karlsruhe (DE)
Bibliographic Reference: Paper presented: Recycling of Plutonium and Uranium in Water Reactor Fuels, Cadarache (FR), Nov. 13-16, 1989
Availability: Available from (1) as Paper EN 35086 ORA
Record Number: 199010478 / Last updated on: 1994-12-01
Category: PUBLICATION
Original language: en
Available languages: en