Irradiation performance of HTGR fertile fuel in HFIR target capsules HT-12 through HT-15. Part I. Experiment description and fission product behavior
Sixteen types of Biso-coated designs, on ThO/sub 2/ kernels, were irradiated in High Flux Isotope Reactor target capsules HT-12 through HT-15. The report addresses the description of the experiment and extensive postirradiation analyses and experiments to determine fertile-particle burnup, fuel coating failures, and fission product behavior. Several low-temperature isotropic (LTI) pyrocarbon coatings, which ''survived'' according to visual inspection, were shown to have developed permeability during irradiation. These particles were irradiated at temperatures approximately equal to 1250/sup 0/C and to burnups equal to or greater than 8 percent fission per initial heavy-metal atom (FIMA). No evidence of permeability was found in similar particles irradiated at temperatures approximately equal to 1550/sup 0/C and burnups approximately equal to 16 percent FIMA. Failures due to permeability were not detectable by visual inspection but required a more extensive investigation by the 1000/sup 0/C gaseous chlorine leaching technique. Maximum particle surface operating temperatures were found to be approximately 300/sup 0/C in excess of design limits of 900/sup 0/C (low-temperature magazines) and 1250/sup 0/C (high-temperature magazines). The extremes of high temperatures and fast neutron fluences up to 1.6 x 10/sup 22/ neutrons/cm/sup 2/ produced severe degradation and swelling of the Poco graphite magazines and sample holders.
- Research Organization:
- Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
- DOE Contract Number:
- W-7405-ENG-26
- OSTI ID:
- 7290593
- Report Number(s):
- ORNL/TM-5305; TRN: 77-011266
- Country of Publication:
- United States
- Language:
- English
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36 MATERIALS SCIENCE
COATED FUEL PARTICLES
PERFORMANCE TESTING
HFIR REACTOR
IRRADIATION CAPSULES
HTGR TYPE REACTORS
THORIUM OXIDES
PHYSICAL RADIATION EFFECTS
BURNUP
COATINGS
FISSION PRODUCT RELEASE
IRRADIATION
PERMEABILITY
PYROLYTIC CARBON
ACTINIDE COMPOUNDS
CARBON
CHALCOGENIDES
ELEMENTS
ENRICHED URANIUM REACTORS
FUEL PARTICLES
GAS COOLED REACTORS
GRAPHITE MODERATED REACTORS
IRRADIATION REACTORS
ISOTOPE PRODUCTION REACTORS
NONMETALS
OXIDES
OXYGEN COMPOUNDS
RADIATION EFFECTS
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
TANK TYPE REACTORS
TEST REACTORS
TESTING
THERMAL REACTORS
THORIUM COMPOUNDS
WATER COOLED REACTORS
WATER MODERATED REACTORS
210300* - Power Reactors
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