Preliminary evaluation of the /sup 233/U refresh cycle hybrid power system concept
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 then using this fuel in a fission reactor without reprocessing. Estimates of the neutronic performance of thorium fusion reactor blankets indicate that adequate concentration of /sup 233/U in thorium can be attained to allow operation of a high temperature gas cooled reactor using nonreprocessed fusion-bred /sup 233/U fuel. Estimates of the fuel materials damage indicate that the breeding and subsequent burning of /sup 233/U can be accomplished within the currently predicted materials limitations of high temperature gas-cooled reactor fuel. The system performance of this symbiotic fusion-fission power system, called the U-233 Refresh Cycle Hybrid Power System, was estimated. A refresh cycle fusion breeder reactor could support from two to three high temperature gas cooled fission burner reactors of equal thermal power without reprocessing. Greatly improved performance is possible if reprocessing is allowed. Thus preliminary evaluation shows that the concept is technically feasible and warrants more detailed study.
- Research Organization:
- General Atomics, San Diego, CA (United States)
- DOE Contract Number:
- EY-76-C-03-0167-038
- OSTI ID:
- 7018241
- Report Number(s):
- GA-A-14940; CONF-780508-15; TRN: 78-015510
- Resource Relation:
- Conference: 3. meeting on the technology of controlled thermonuclear fusion, Santa Fe, NM, USA, 9 May 1978
- Country of Publication:
- United States
- Language:
- English
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