Fission product tellurium release behavior under severe light water reactor accident conditions
Fission product release tests and control tests recently conducted at Oak Ridge National Laboratory have provided new experimental data that help characterize the mechanism of fission product tellurium release behavior under severe light water reactor accident conditions. Release of tellurium from the fuel rod segments has been found to be dependent on the rate and extent of cladding oxidation. Tellurium was observed to be significantly retained by metallic Zircaloy cladding at test temperatures up to 2000/sup 0/C. The results indicate that the tellurium was bound by the Zircaloy cladding as zirconium telluride, but once the available metallic zirconium was oxidized by the steam, tellurium was released in favor of continued zirconium oxide formation. The collection behavior of the released tellurium indicated that it was probably released from the fuel rods as tellurides of tin, cesium, and rubidium rather than as elemental tellurium.
- Research Organization:
- Oak Ridge National Lab., Chemical Technology Div., P.O. Box X, Building 4501, Oak Ridge, TN 37831-6221 (USA)
- OSTI ID:
- 5316193
- Journal Information:
- Nucl. Technol.; (United States), Vol. 77:1
- Country of Publication:
- United States
- Language:
- English
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21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
TELLURIUM
MONITORING
WATER COOLED REACTORS
FISSION PRODUCT RELEASE
REACTOR ACCIDENTS
CESIUM TELLURIDES
FISSION PRODUCTS
FUEL RODS
FUEL-CLADDING INTERACTIONS
ORNL
OXIDATION
REACTOR SAFETY
RUBIDIUM TELLURIDES
TESTING
TIN TELLURIDES
VERY HIGH TEMPERATURE
ZIRCALOY
ZIRCONIUM TELLURIDES
ACCIDENTS
ALKALI METAL COMPOUNDS
ALLOYS
CESIUM COMPOUNDS
CHALCOGENIDES
CHEMICAL REACTIONS
ELEMENTS
FUEL ELEMENTS
ISOTOPES
MATERIALS
NATIONAL ORGANIZATIONS
RADIOACTIVE MATERIALS
REACTOR COMPONENTS
REACTORS
RUBIDIUM COMPOUNDS
SAFETY
SEMIMETALS
TELLURIDES
TELLURIUM COMPOUNDS
TIN ALLOYS
TIN COMPOUNDS
TRANSITION ELEMENT COMPOUNDS
US AEC
US DOE
US ERDA
US ORGANIZATIONS
ZIRCONIUM ALLOYS
ZIRCONIUM BASE ALLOYS
ZIRCONIUM COMPOUNDS
220900* - Nuclear Reactor Technology- Reactor Safety
210100 - Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 - Power Reactors
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Nonboiling Water Cooled