Peach Bottom test element program. Final report
Thirty-three test elements were irradiated in the Peach Bottom high-temperature gas-cooled reactor (HTGR) as part of the testing program for advanced HTGRs. Extensive postirradiation examinations and evaluations of 21 of these irradiation experiments were performed. The test element irradiations were simulated using HTGR design codes and data. Calculated fuel burnups, power profiles, fast neutron fluences, and temperatures were verified via destructive burnup measurements, gamma scanning, and in-pile thermocouple readings corrected for decalibration effects. Analytical techniques were developed to improve the quality of temperature predictions through feedback of nuclear measurements into thermal calculations. Dimensional measurements, pressure burst tests, diametral compression tests, ring-cutting tests, strip-cutting tests, and four-point bend tests were performed to measure residual stress, strain, and strength distributions in H-327 graphite structures irradiated in the test elements.
- Research Organization:
- General Atomics, San Diego, CA (United States)
- DOE Contract Number:
- AT03-76ET35300
- OSTI ID:
- 6347913
- Report Number(s):
- GA-A-15999; ON: DE83009706
- Resource Relation:
- Other Information: Portions are illegible in microfiche products. Original copy available until stock is exhausted
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
PEACH BOTTOM-1 REACTOR
FUEL RODS
BURNUP
COATED FUEL PARTICLES
DEFORMATION
FAILURES
FISSION PRODUCT RELEASE
FISSION PRODUCTS
MICROSTRUCTURE
NEUTRON FLUX
PERFORMANCE TESTING
STRAINS
STRESSES
THORIUM CARBIDES
THORIUM OXIDES
URANIUM CARBIDES
URANIUM DIOXIDE
ACTINIDE COMPOUNDS
CARBIDES
CARBON COMPOUNDS
CHALCOGENIDES
CRYSTAL STRUCTURE
ENRICHED URANIUM REACTORS
FUEL ELEMENTS
FUEL PARTICLES
GAS COOLED REACTORS
GRAPHITE MODERATED REACTORS
HELIUM COOLED REACTORS
HTGR TYPE REACTORS
ISOTOPES
MATERIALS
OXIDES
OXYGEN COMPOUNDS
POWER REACTORS
RADIATION FLUX
RADIOACTIVE MATERIALS
REACTOR COMPONENTS
REACTORS
TESTING
THERMAL REACTORS
THORIUM COMPOUNDS
URANIUM COMPOUNDS
URANIUM OXIDES
210300* - Power Reactors
Nonbreeding
Graphite Moderated