Recommended CRBRP reload core designs using (U--Pu)C fuel
Conference
·
· Trans. Am. Nucl. Soc.; (United States)
OSTI ID:6805587
None
- Research Organization:
- Atomics International, Canoga Park, CA
- OSTI ID:
- 6805587
- Conference Information:
- Journal Name: Trans. Am. Nucl. Soc.; (United States) Journal Volume: 28
- Country of Publication:
- United States
- Language:
- English
Similar Records
Advanced fuel core designs for CRBRP
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Final design analyses of CRBRP fuel rod
Conference
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Fri Dec 31 23:00:00 EST 1976
· Trans. Am. Nucl. Soc.; (United States)
·
OSTI ID:5357386
Design of reload cores using optimal control theory. [PWR]
Conference
·
Fri Dec 31 23:00:00 EST 1976
· Trans. Am. Nucl. Soc.; (United States)
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Final design analyses of CRBRP fuel rod
Conference
·
Mon Dec 31 23:00:00 EST 1979
· Trans. Am. Nucl. Soc.; (United States)
·
OSTI ID:6887237
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210500* -- Power Reactors
Breeding
ACTINIDE COMPOUNDS
BREEDER REACTORS
CARBIDES
CARBON COMPOUNDS
CLINCH RIVER BREEDER REACTOR
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FUEL ASSEMBLIES
KINETICS
LIQUID METAL COOLED REACTORS
PLUTONIUM CARBIDES
PLUTONIUM COMPOUNDS
POWER REACTORS
REACTIVITY WORTHS
REACTOR COMPONENTS
REACTOR CORES
REACTOR KINETICS
REACTORS
SODIUM COOLED REACTORS
TRANSURANIUM COMPOUNDS
URANIUM CARBIDES
URANIUM COMPOUNDS
210500* -- Power Reactors
Breeding
ACTINIDE COMPOUNDS
BREEDER REACTORS
CARBIDES
CARBON COMPOUNDS
CLINCH RIVER BREEDER REACTOR
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FUEL ASSEMBLIES
KINETICS
LIQUID METAL COOLED REACTORS
PLUTONIUM CARBIDES
PLUTONIUM COMPOUNDS
POWER REACTORS
REACTIVITY WORTHS
REACTOR COMPONENTS
REACTOR CORES
REACTOR KINETICS
REACTORS
SODIUM COOLED REACTORS
TRANSURANIUM COMPOUNDS
URANIUM CARBIDES
URANIUM COMPOUNDS