TRIGA high wt -% LEU fuel development program. Final report
The principal purpose of this work was to investigate the characteristics of TRIGA fuel where the contained U-235 was in a relatively high weight percent (wt %) of LEU (low enriched uranium - enrichment of less than 20%) rather than a relatively low weight percent of HEU (high enriched uranium). Fuel with up to 45 wt % U was fabricated and found to be acceptable after metallurgical examinations, fission product retention tests and physical property examinations. Design and safety analysis studies also indicated acceptable prompt negative temperature coefficient and core lifetime characteristics for these fuels.
- Research Organization:
- General Atomic Co., San Diego, CA (USA)
- DOE Contract Number:
- AT03-76SF70064
- OSTI ID:
- 6930597
- Report Number(s):
- GA-A-15972
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
220600* -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
ENRICHED URANIUM REACTORS
FABRICATION
FISSION PRODUCT RELEASE
FUEL ELEMENTS
HOMOGENEOUS REACTORS
HYDRIDE MODERATED REACTORS
METALLURGY
PHYSICAL PROPERTIES
REACTOR COMPONENTS
REACTORS
RESEARCH AND TEST REACTORS
SOLID HOMOGENEOUS REACTORS
TRIGA TYPE REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
220600* -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
ENRICHED URANIUM REACTORS
FABRICATION
FISSION PRODUCT RELEASE
FUEL ELEMENTS
HOMOGENEOUS REACTORS
HYDRIDE MODERATED REACTORS
METALLURGY
PHYSICAL PROPERTIES
REACTOR COMPONENTS
REACTORS
RESEARCH AND TEST REACTORS
SOLID HOMOGENEOUS REACTORS
TRIGA TYPE REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS