Behaviour of MOX fuel irradiated under normal and transient conditions
Fuel restructuring, the redistribution of Pu and the behaviour of Xe and Cs have been investigated in three segments of MOX fuel. Two of the segments had been irradiated under normal conditions to burn-ups of 23.2 and 38.8 GWd/t; the third had been transient-tested to 42 kW/m, for 52.2 h at 26.2 GWd/t. The fuel was fabricated by the AUPuC process, which involved mechanically blending a master-mix of 70/30 UO(2)-PuO(2) with natural UO(2) powder. The product contained nominally 3.2 wt% Pu and consisted of agglomerates of master-mix particles less than 100 microns in size, irregularly dispersed in a matrix of UO(2). The local concentrations of Pu, Xe and Cs were determined by electron probe microanalysis (EPMA). The volume fraction of pores and large bubbles in the MOX agglomerates and UO(2) matrix was measured using a Leitz quantitative image analyser, connected to a Reichert Telatom 62 optical microscope.
Bibliographic Reference: Paper presented: Jahrestagung Kerntechnik 1990, Nuernberg (DE), May 15-17, 1990
Availability: Available from (1) as Paper EN 35242 ORA
Record Number: 199010877 / Last updated on: 1994-12-01
Original language: en
Available languages: en