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Cladding properties under simulated fuel pin transients. [LMFBR]

Conference ·
OSTI ID:7191852
;
A description is given of the HEDL fuel pin testing program utilizing a recently developed Fuel Cladding Transient Tester (FCTT) to generate the requisite mechanical property information on irradiated and unirradiated fast reactor fuel cladding under temperature ramp conditions. The test procedure is described, and data are presented.
Research Organization:
Hanford Engineering Development Lab., Richland, Wash. (USA)
DOE Contract Number:
E(45-1)-2170
OSTI ID:
7191852
Report Number(s):
HEDL-SA-1028; CONF-7510107-1
Country of Publication:
United States
Language:
English

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Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210500* -- Power Reactors
Breeding
ACCIDENTS
BREEDER REACTORS
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FUEL CANS
FUEL ELEMENT FAILURE
FUEL ELEMENTS
FUEL PINS
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
PERFORMANCE TESTING
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTORS
SIMULATION
TEMPERATURE GRADIENTS
TESTING
TRANSIENTS