FAILURE THRESHOLD TREAT EXPERIMENT WITH AN UNIRRADIATED PROTOTYPICAL FFTF FUEL ELEMENT.
Journal Article
·
· Trans. Amer. Nucl. Soc. 13: 652(Nov 1970).
OSTI ID:4094571
- Research Organization:
- Argonne National Lab., Ill.); (and others)
- NSA Number:
- NSA-25-006096
- OSTI ID:
- 4094571
- Journal Information:
- Trans. Amer. Nucl. Soc. 13: 652(Nov 1970)., Other Information: From Meeting of the American Nuclear Society, Washington, D. C. See CONF- 701102. Orig. Receipt Date: 31-DEC-71
- Country of Publication:
- Country unknown/Code not available
- Language:
- English
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Related Subjects
N38550* -Research & Test Reactors & Critical Assemblies- Fuels
FAILURES
FAST REACTORS
FTR
FUEL ELEMENTS
FUEL PINS
PLUTONIUM OXIDES
REACTOR SAFETY
RESEARCH REACTORS
RODS
TESTING
TREAT
URANIUM DIOXIDE
REACTORS
LIQUID METAL-COOLED/fuel element failure limits for sodium
oxide pin type
FAST TEST REACTOR/fuel elements for
failure limits for mixed oxide pin type
REACTOR SAFETY EXPERIMENTS/fuel elements in TREAT
failure limits for mixed oxide pin type
REACTOR FUEL ELEMENTS/failure limits for liquid sodium cooled mixed oxide pin type
FAILURES
FAST REACTORS
FTR
FUEL ELEMENTS
FUEL PINS
PLUTONIUM OXIDES
REACTOR SAFETY
RESEARCH REACTORS
RODS
TESTING
TREAT
URANIUM DIOXIDE
REACTORS
LIQUID METAL-COOLED/fuel element failure limits for sodium
oxide pin type
FAST TEST REACTOR/fuel elements for
failure limits for mixed oxide pin type
REACTOR SAFETY EXPERIMENTS/fuel elements in TREAT
failure limits for mixed oxide pin type
REACTOR FUEL ELEMENTS/failure limits for liquid sodium cooled mixed oxide pin type