Effect of carbon impurity during the sintering of MOX fuels
Creators
- 1. CEA - Centre de Marcoule, DEN, DTEC, SECA, LFC, F-30207 Bagnols sur Ceze (France)
- 2. CEA - Centre de Marcoule, DEN, DTEC, SECA, LCC, F-30207 Bagnols sur Ceze (France)
Description
UO2 and PuO2 powders are currently used as raw materials for the industrial fabrication of mixed uranium plutonium oxide (MOX) for light-water reactors. The mixture is pelletized before being sintered at 1700 Celsius degrees under a reducing atmosphere of Ar/4%H2 with 1200 vpm H2O. At the end of the oxide ceramic sintering process, a swelling phenomenon sometimes occurs and could be responsible for the fuel non-compliance with safety specifications. This phenomenon is often caused by the presence of carbon impurities in the raw materials. In this paper, it will be shown how carbon impurities (naturally present or deliberately introduced) in the raw materials affect MOX fuel densification by sintering. For that purpose, MOX densification has been monitored by dilatometric measurements and the gases released during sintering have been continuously qualitatively and quantitatively analyzed. Gases released or trapped in the fuel during densification have been studied, as well as the sintered fuel characteristics (density, microstructure, U/Pu distribution). Results confirm that carbon impurities can play a major role in the fuel swelling: the oxides react with carbon and form gaseous CO molecules that could be trapped in the closed pores during sintering. This leads to a pressure increase within pores responsible for an irreversible swelling by creep deformation. (authors)
Availability note (English)
Available from: American Nuclear Society - ANS, 555 North Kensington Avenue, La Grange Park, IL 60526 (US), also available in CD-RomAdditional details
Publishing Information
- Publisher
- American Nuclear Society - ANS
- Imprint Place
- La Grange Park, IL (United States)
- ISBN
- 978-0-89448-734-7
- Imprint Title
- TOP FUEL 2016 Proceedings
- Imprint Pagination
- 1670 p.
- Journal Page Range
- p. 975-982
Conference
- Title
- LWR fuels with enhanced safety and performance
- Acronym
- TOP FUEL 2016
- Dates
- 11-15 Sep 2016
- Place
- Boise, ID (United States)
INIS
- Country of Publication
- United States
- Country of Input or Organization
- France
- INIS RN
- 50007238
- Subject category
- S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CARBON; CARBON MONOXIDE; CREEP; FISSION POISONS; FISSION PRODUCT RELEASE; FUEL DENSIFICATION; IMPURITIES; MICROSTRUCTURE; MIXED OXIDE FUELS; PLUTONIUM; PLUTONIUM OXIDES; RAW MATERIALS; SINTERING; SWELLING; TEMPERATURE RANGE 1000-4000 K; TRAPPING; URANIUM; URANIUM DIOXIDE; WATER COOLED REACTORS; WATER MODERATED REACTORS
- Descriptors DEC
- ACTINIDE COMPOUNDS; ACTINIDES; CARBON COMPOUNDS; CARBON OXIDES; CHALCOGENIDES; DEFORMATION; ELEMENTS; ENERGY SOURCES; FABRICATION; FUELS; MATERIALS; MECHANICAL PROPERTIES; METALS; NONMETALS; NUCLEAR FUELS; NUCLEAR POISONS; OXIDES; OXYGEN COMPOUNDS; PLUTONIUM COMPOUNDS; REACTOR MATERIALS; REACTORS; SOLID FUELS; TEMPERATURE RANGE; TRANSURANIUM COMPOUNDS; TRANSURANIUM ELEMENTS; URANIUM COMPOUNDS; URANIUM OXIDES
Optional Information
- Notes
- 11 refs.