Published July 1985
| Version v1
Report
Relationship between fuel element power and the leaching of 137Cs and 129I from irradiated UO2 fuel
Creators
- 1. Whiteshell Nuclear Research Establishment, Pinawa, Manitoba
Description
The release of 137Cs and 129I from UO2 fuel element sections (typical of CANDU type reactors) exposed to water at 250C and at 1500C has been studied as a function of fuel irradiation history. The relationships between the quantities of these nuclides leached at 250C and the stable xenon release at the end of fuel irradiation are discussed. The results indicate that gap inventories of these nuclides are equal to or less than gap inventories of stable xenon. Preliminary evidence for the rapid leaching, at 1500C, of a fraction of the grain boundary inventory of 137Cs and 129I is also presented
Additional details
Publishing Information
- Imprint Title
- American Nuclear Society meeting on fission-product behavior and source term research: proceedings
- Journal Page Range
- p. 15.1-15.12.
- Report number
- EPRI-NP--4113-SR
Conference
- Title
- Topical meeting on fission product behavior and source term research.
- Dates
- 15-19 Jul 1984.
- Place
- Snowbird, UT (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 19023826
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- BURNUP; CANDU TYPE REACTORS; CESIUM 137; FISSION PRODUCT RELEASE; FUEL ELEMENT FAILURE; FUEL ELEMENTS; GAS CHROMATOGRAPHY; GRAIN BOUNDARIES; IODINE 129; IRRADIATION; LEACHING; LOSS OF COOLANT; MEDIUM TEMPERATURE; OXIDATION; REACTOR ACCIDENTS; REACTOR SAFETY; THERMAL SHOCK; URANIUM DIOXIDE; WATER; XENON; ZIRCALOY
- Descriptors DEC
- ACCIDENTS; ACTINIDE COMPOUNDS; ALLOYS; BETA DECAY RADIOISOTOPES; BETA-MINUS DECAY RADIOISOTOPES; CESIUM ISOTOPES; CHALCOGENIDES; CHEMICAL REACTIONS; CHROMATOGRAPHY; CRYSTAL STRUCTURE; DISSOLUTION; ELEMENTS; HEAVY WATER MODERATED REACTORS; HYDROGEN COMPOUNDS; INTERMEDIATE MASS NUCLEI; INTERNAL CONVERSION RADIOISOTO; IODINE ISOTOPES; ISOTOPES; MICROSTRUCTURE; NONMETALS; NUCLEI; ODD-EVEN NUCLEI; OXIDES; OXYGEN COMPOUNDS; POLAR SOLVENTS; POWER REACTORS; PRESSURE TUBE REACTORS; RADIOISOTOPES; RARE GASES; REACTOR COMPONENTS; REACTORS; SAFETY; SEPARATION PROCESSES; SOLVENTS; THERMAL REACTORS; URANIUM COMPOUNDS; URANIUM OXIDES; YEARS LIVING RADIOISOTOPES; ZIRCONIUM ALLOYS; ZIRCONIUM BASE ALLOYS