Behavior of fission product tellurium under severe accident conditions
Fission product release tests at Oak Ridge National Laboratory (ORNL) have provided new experimental data that help characterize the behavior of tellurium under severe light-water reactor (LWR) accident conditions. The release of tellurium from the fuel rods is dependent upon the rate and extent of cladding oxidation. Tellurium has been found to be considerably retained by metallic Zircaloy cladding at test temperatures up to 1975/sup 0/C. The results indicate that the tellurium is bound by the Zircaloy cladding as zirconium telluride, but once the available zirconium metal is oxidized by the steam, tellurium is released in favor of continued zirconium oxide formation. The collection behavior of the released tellurium indicates that it is probably released from the fuel rods as SnTe and CsTe, rather than as elemental tellurium.
- Research Organization:
- Oak Ridge National Lab., TN (USA)
- DOE Contract Number:
- AC05-84OR21400
- OSTI ID:
- 6188157
- Report Number(s):
- CONF-860204-17; ON: TI86004788
- Resource Relation:
- Conference: International ANS/ENS topical meeting on thermal reactor safety, San Diego, CA, USA, 2 Feb 1986
- Country of Publication:
- United States
- Language:
- English
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21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
BWR TYPE REACTORS
FUEL CANS
FUEL RODS
REACTOR ACCIDENTS
FISSION PRODUCT RELEASE
PWR TYPE REACTORS
FISSION PRODUCTS
REACTOR SAFETY
RISK ASSESSMENT
TELLURIUM
ZIRCALOY
ACCIDENTS
ALLOYS
ELEMENTS
FUEL ELEMENTS
ISOTOPES
MATERIALS
RADIOACTIVE MATERIALS
REACTOR COMPONENTS
REACTORS
SAFETY
SEMIMETALS
TIN ALLOYS
WATER COOLED REACTORS
WATER MODERATED REACTORS
ZIRCONIUM ALLOYS
ZIRCONIUM BASE ALLOYS
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210100 - Power Reactors
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210200 - Power Reactors
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