AN EVALUATION OF U$sup 233$ THORIUM FAST BREEDER POWER REACTORS
A study of fast U/sup 233/-Th breeders was performed. Comparative evaluation of potential fuels for fast U/sup 233/-Th/sup 232/ breeders resulted in the selection of carbide fuel based on minimum fuel costs and attractive doubling time. A reference design of a 300 MW/sub e/ carbide-fueled reactor plant yielded an energy cost of 9.1 mill/kwh for a fuel burnup of 50,000 MW-d/ tonne. At equilibrium fuel cycle conditions, the reference design has a breeding ratio of 1.31 and a total inventory doubling time of 23 yr. Unique characteristics of U/sup 233/-Th fueled fast breeders such as continued buildup of reactivity after shutdown, the requirement for remote handling of fresh fuel, and the low delayed neutron fraction, were considered. It was concluded that these characteristics can be accommodated by appropriate design features without appreciably affecting either power generation cost or safety of operation. A comparison of the reference carbide-fueled design with a plutonium oxide-fueled fast breeder indicated comparable power generation costs and doubling times. In comparison with U/sup 233/-fueled, thermal homogeneous breeders, the fast U/sup 233/ breeder offers lower power generation cost (9.1 as against 10.6 mill/kwh for the thermal breeder) but longer doubling time (23 yr as against 6 to 20 yr for the thermal breeder). (auth)
- Research Organization:
- United Nuclear Corp. Development Div., White Plains, N.Y.
- NSA Number:
- NSA-16-026613
- OSTI ID:
- 4823187
- Report Number(s):
- NDA-2164-3
- Country of Publication:
- United States
- Language:
- English
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