/sup 233/U fusion--fission power system without reprocessing: a preliminary report
A preliminary evaluation was made of the technical feasibility of using a fusion reactor to breed /sup 233/U from thorium in high temperature gas cooled fission reactor fuel and of then using this fuel in a fission reactor without reprocessing. Estimates of the neutronic performance of thorium fusion reactor blankets were made. The fuel cycle characteristics of high temperature gas-cooled reactors operating on nonreprocessed fusion-bred /sup 233/U fuel were also estimated. The system performance of symbiotic fusion-fission power systems without reprocessing was then determined.
- Research Organization:
- General Atomic Co., San Diego, Calif. (USA)
- DOE Contract Number:
- EY-76-C-03-0167-038
- OSTI ID:
- 5271616
- Report Number(s):
- GA-A-14635
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700201* -- Fusion Power Plant Technology-- Blanket Engineering
ACTINIDE ISOTOPES
ACTINIDE NUCLEI
ALPHA DECAY RADIOISOTOPES
BREEDING
BREEDING BLANKETS
EVEN-EVEN NUCLEI
EVEN-ODD NUCLEI
FEASIBILITY STUDIES
FUEL CYCLE
GAS COOLED REACTORS
HEAVY NUCLEI
HYBRID REACTORS
ISOTOPES
NUCLEAR FUEL CONVERSION
NUCLEI
RADIOISOTOPES
REACTOR COMPONENTS
REACTORS
REPROCESSING
SEPARATION PROCESSES
THORIUM 232
THORIUM ISOTOPES
URANIUM 233
URANIUM ISOTOPES
YEARS LIVING RADIOISOTOPES
700201* -- Fusion Power Plant Technology-- Blanket Engineering
ACTINIDE ISOTOPES
ACTINIDE NUCLEI
ALPHA DECAY RADIOISOTOPES
BREEDING
BREEDING BLANKETS
EVEN-EVEN NUCLEI
EVEN-ODD NUCLEI
FEASIBILITY STUDIES
FUEL CYCLE
GAS COOLED REACTORS
HEAVY NUCLEI
HYBRID REACTORS
ISOTOPES
NUCLEAR FUEL CONVERSION
NUCLEI
RADIOISOTOPES
REACTOR COMPONENTS
REACTORS
REPROCESSING
SEPARATION PROCESSES
THORIUM 232
THORIUM ISOTOPES
URANIUM 233
URANIUM ISOTOPES
YEARS LIVING RADIOISOTOPES