Published 1979
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Fission gas release from UO2 pellet fuel at high burn-up
Description
Analysis of in-reactor measurements of fuel center temperature and rod internal pressure at the OECD Halden Reactor Project has led to the development of an empirical fission gas release model, which is described. The model originally derived from data obtained in the low and intermediate burn-up range, appears to give good predictions for rods irradiated to high exposures as well. PIE puncturing data from seven fuel rods, operated at relatively constant powers and peak center temperatures between 1900 and 20000C up to approx. 40,000 MWd/t UO2, did not exhibit any burn-up enhancement on the fission gas release rate
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Additional details
Additional titles
- Augmented title (English)
- BWR; PWR
Publishing Information
- Imprint Title
- Proceedings of American Nuclear Society topical meeting on light water reactor fuel performance
- Journal Page Range
- p. 361-366.
- Report number
- DOE/ET/34007--1
Conference
- Title
- ANS topical meeting on light water reactor fuel performance.
- Dates
- 29 Apr - 2 May 1979.
- Place
- Portland, OR, USA.
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 11544784
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BURNUP; BWR TYPE REACTORS; FISSION PRODUCT RELEASE; FUEL PELLETS; PWR TYPE REACTORS; URANIUM DIOXIDE
- Descriptors DEC
- ACTINIDE COMPOUNDS; CHALCOGENIDES; OXIDES; OXYGEN COMPOUNDS; REACTORS; URANIUM COMPOUNDS; URANIUM OXIDES; WATER COOLED REACTORS; WATER MODERATED REACTORS