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/sup 233/U fusion--fission power system without reprocessing: a preliminary report

Technical Report ·
DOI:https://doi.org/10.2172/5271616· OSTI ID:5271616
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