Postirradiation examination and evaluation of Peach Bottom fuel test elements FTE-14 and FTE-15
Peach Bottom fuel test elements FTE-14 and FTE-15 were companion nonaccelerated tests of fuel rods and fuel particles representative of the Large High-Temperature Gas-Cooled Reactor (LHTGR). The purpose of the tests was to broaden the data base of H-327 graphite and various fuel types; specifically, UO/sub 2/, UC/sub 2/, weak acid resin UC/sub x//O/sub y/, and several fertile fuel types were tested. The irradiation reached peak fuel temperatures of 1600/sup 0/C volume- and time-averaged temperatures of 1300/sup 0/C, and fast fluence exposures up to 2 x 10/sup 25/ n/m/sup 2/ (E > 29 fJ)/sub HTGR/. Experimental results were compared with predictions based on accelerated irradiation tests, postirradiation heating, and other Peach Bottom test elements to validate HTGR design codes. The nuclear design predictions were modified by measurements which allowed the verification of thermal design calculations and thermocouple readings.
- Research Organization:
- General Atomics, San Diego, CA (United States)
- DOE Contract Number:
- EY-76-C-03-0167-065
- OSTI ID:
- 6310141
- Report Number(s):
- GA-A-13944; TRN: 79-010407
- Country of Publication:
- United States
- Language:
- English
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36 MATERIALS SCIENCE
COATED FUEL PARTICLES
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PEACH BOTTOM-1 REACTOR
FUEL ELEMENTS
THORIUM CARBIDES
THORIUM OXIDES
URANIUM CARBIDES
URANIUM DIOXIDE
PERFORMANCE TESTING
STRAINS
STRESSES
TEMPERATURE DISTRIBUTION
ACTINIDE COMPOUNDS
CARBIDES
CARBON COMPOUNDS
CHALCOGENIDES
ENRICHED URANIUM REACTORS
FUEL PARTICLES
GAS COOLED REACTORS
GRAPHITE MODERATED REACTORS
HELIUM COOLED REACTORS
HTGR TYPE REACTORS
OXIDES
OXYGEN COMPOUNDS
POWER REACTORS
RADIATION EFFECTS
REACTOR COMPONENTS
REACTORS
TESTING
THERMAL REACTORS
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URANIUM COMPOUNDS
URANIUM OXIDES
210300* - Power Reactors
Nonbreeding
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