Published May 1997 | Version v1
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Cation diffusion and crystal growth at the UO2-PuO2 interface

  • 1. Laboratoire des Ceramiques Nucleaires, Centre d'Etudes Nucleaires de Cadarache, Saint-Paul-lez-Durance (France)

Description

A better understanding of the homogenizing phenomena involved in the dry route fabrication of MOX fuel has led to the study of interdiffusion coefficients of plutonium and uranium during the sintering. Interdiffusion coefficients have been calculated from electron microprobe analysis of diffusion couples UO2 (green compact)/ PuO2 (green compact). A series of these diffusion couples has been sintered at 1773, 1873 and 2023K during 0 to 50 hours and under controlled oxygen potential (-88, -95 and -125 kcal/mol). The results show that grain-boundary diffusion predominates, essentially at the end of the intermediate stage of the sintering. On the opposite, the lattice diffusion is very slow. The sintering and particularly the crystal growth enhance the interdiffusion coefficients which are slightly greater compared to those of polycrystalline diffusion couples. (author). 6 refs, 5 figs

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Part of:
Recycling of plutonium and uranium in water reactor fuel. Proceedings of a technical committee meeting

Additional details

Publishing Information

Imprint Title
Recycling of plutonium and uranium in water reactor fuel. Proceedings of a technical committee meeting
Imprint Pagination
391 p.
Journal Page Range
p. 113-118.
ISSN
1011-4289
Report number
IAEA-TECDOC--941

Conference

Title
Technical committee meeting on recycling of plutonium and uranium in water reactor fuel.
Dates
3-7 Jul 1995.
Place
Newby Bridge, Windermere (United Kingdom).

INIS

Country of Publication
International Atomic Energy Agency (IAEA)
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
28047125
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
CATIONS; CRYSTAL GROWTH; DIFFUSION; FABRICATION; HOMOGENIZATION METHODS; MIXED OXIDE FUELS; PLUTONIUM DIOXIDE; SINTERING; URANIUM DIOXIDE
Descriptors DEC
ACTINIDE COMPOUNDS; CALCULATION METHODS; CHALCOGENIDES; CHARGED PARTICLES; ENERGY SOURCES; FUELS; IONS; MATERIALS; NUCLEAR FUELS; OXIDES; OXYGEN COMPOUNDS; PLUTONIUM COMPOUNDS; PLUTONIUM OXIDES; REACTOR MATERIALS; SOLID FUELS; TRANSURANIUM COMPOUNDS; URANIUM COMPOUNDS; URANIUM OXIDES

Optional Information