Core design calculations for MEU fuel in FSV
Results of a study on the feasibility of converting the Fort St. Vrain reactor core from the present 6-year, High Enriched Uranium (HEU) fuel cycle using uranium enriched to 93% U-235 and thorium to a 6-year, Medium Enriched Uranium (MEU) fuel cycle using uranium enriched to 20% U-235 and thorium, are described. The study shows that a transition from the HEU to MEU cycle can be accomplished, and that operation of the FSV core on a straight MEU cycle is feasible within present Tech. Spec. limits.
- Research Organization:
- General Atomic Co., San Diego, CA (USA)
- DOE Contract Number:
- EY-76-C-03-0167-065
- OSTI ID:
- 5594987
- Report Number(s):
- GA-A-15258
- Country of Publication:
- United States
- Language:
- English
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FUEL CYCLE
GAS COOLED REACTORS
GRAPHITE MODERATED REACTORS
HELIUM COOLED REACTORS
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210300* -- Power Reactors
Nonbreeding
Graphite Moderated
210802 -- Nuclear Power Plants-- Economics-- Fuel Cycle
BURNUP
CROSS SECTIONS
EFFICIENCY
ENRICHED URANIUM REACTORS
FEASIBILITY STUDIES
FUEL CYCLE
GAS COOLED REACTORS
GRAPHITE MODERATED REACTORS
HELIUM COOLED REACTORS
HTGR TYPE REACTORS
KINETICS
OPERATION
POWER DISTRIBUTION
POWER REACTORS
REACTOR COMPONENTS
REACTOR CORES
REACTOR KINETICS
REACTOR OPERATION
REACTORS
VRAIN REACTOR