Postirradiation examination and evaluation of Peach Bottom fuel test element FTE-6
Fuel test element FTE-6 was irradiated in the Peach Bottom high-temperature gas-cooled reactor (HTGR) for 645 equivalent full power days. Four fuel varieties, contained in H-327 graphite bodies, were tested. A primary result of this test has been to demonstrate acceptable performance even with calculated high stresses in the graphite bodies. Heterogeneous fuel loadings in the element caused local power peaking and azimuthal power variations, deforming the graphite fuel bodies and thereby causing bowing nearly five times as large as the diametral clearance within the sleeve. The axial stresses resulting from interference between the fuel bodies and sleeve were estimated to have reached 45% of the ultimate material strength at the end of the irradiation. Residual stresses from differential contraction within the fuel body resulted in probable in-plane stress levels of 130% of the material strength at the end-of-life shutdown and of up to 150% of the strength at shutdown during the irradiation cycle. The high in-plane stresses are local peaks at the corners of a sharp notch in the element, which may account for the stresses failing to cause damage. The lack of observable damage, however, indicates that the methods and data used for stress analysis give results that are either fairly accurate or conservative.
- Research Organization:
- General Atomics, San Diego, CA (United States)
- DOE Contract Number:
- EY-76-C-03-0167
- OSTI ID:
- 5412543
- Report Number(s):
- GA-A-13943; TRN: 78-002600
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
36 MATERIALS SCIENCE
GRAPHITE
PHYSICAL RADIATION EFFECTS
PEACH BOTTOM-1 REACTOR
FUEL ELEMENTS
BURNUP
COATED FUEL PARTICLES
IRRADIATION
PERFORMANCE TESTING
CARBON
ELEMENTS
ENRICHED URANIUM REACTORS
FUEL PARTICLES
GAS COOLED REACTORS
GRAPHITE MODERATED REACTORS
HELIUM COOLED REACTORS
HTGR TYPE REACTORS
NONMETALS
POWER REACTORS
RADIATION EFFECTS
REACTOR COMPONENTS
REACTORS
TESTING
THERMAL REACTORS
210300* - Power Reactors
Nonbreeding
Graphite Moderated
360605 - Materials- Radiation Effects