Measurement and modelling of postirradiation fission product release from HTGR fuel particles under accident conditions
A study was performed to provide a description of the release of fission products from failed fuel particles during a core heatup event in an HTGR. The need for this study was established in the Accident Initiation and Progression Analysis program. The release of fission products was measured from laser-failed BISO ThO/sub 2/, TRISO UC/sub 2/, and weak acid resin (WAR) particles over a range of burnups. The burnups were 0.25, 1.4 and 15.7% FIMA for ThO/sub 2/ particles, 23.5 and 74% FIMA for UC/sub 2/ particles, and 60% FIMA for WAR particles. The fission products measured were nuclides of xenon, iodine, krypton, tellurium, and cesium. Two types of experiments were performed: isothermal and temperature rise experiments. The range of the temperatures was from 1200/sup 0/ to 2300/sup 0/C. In the temperature rise experiments, the heating rates were between 50/sup 0/ and 450/sup 0/C/h.
- Research Organization:
- General Atomic Co., San Diego, CA (USA)
- DOE Contract Number:
- EY-76-C-03-0167-065
- OSTI ID:
- 6495626
- Report Number(s):
- GA-A-15018
- Country of Publication:
- United States
- Language:
- English
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21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210300* -- Power Reactors
Nonbreeding
Graphite Moderated
ACCIDENTS
ACTINIDE COMPOUNDS
CARBIDES
CARBON COMPOUNDS
CHALCOGENIDES
COATED FUEL PARTICLES
FISSION PRODUCT RELEASE
FUEL ELEMENT FAILURE
FUEL PARTICLES
GAS COOLED REACTORS
GRAPHITE MODERATED REACTORS
HTGR TYPE REACTORS
OXIDES
OXYGEN COMPOUNDS
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URANIUM CARBIDES
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210300* -- Power Reactors
Nonbreeding
Graphite Moderated
ACCIDENTS
ACTINIDE COMPOUNDS
CARBIDES
CARBON COMPOUNDS
CHALCOGENIDES
COATED FUEL PARTICLES
FISSION PRODUCT RELEASE
FUEL ELEMENT FAILURE
FUEL PARTICLES
GAS COOLED REACTORS
GRAPHITE MODERATED REACTORS
HTGR TYPE REACTORS
OXIDES
OXYGEN COMPOUNDS
REACTOR ACCIDENTS
REACTORS
THORIUM COMPOUNDS
THORIUM OXIDES
URANIUM CARBIDES
URANIUM COMPOUNDS