Molten salt fast thermal reactor system with no waste
Technical Report
·
OSTI ID:4938199
A power system of 1 GW(e) containing a fast breeder reactor (2GW(t)) with a molten chloride fuel and a thermal burner reactor (~0.5 GW(t)) with molten fluoride fuel resulting in a total breeding system with a doubling time of 30 years is described. The fast breeder works on a U-238/Pu-239 cycle, the thermal burner on Pu-239. The thermal burner incinerates'' (by neutron transformation) most of the long lived fission products: Kr-85, Sr-90, Tc99, Cs-135 and other. The actinides (Np, Am, Cm) might be recovered from the molten salt with a high efficiency and then burned in the fast reactor. The fast reactor has an inherent stability against power excursions, and loss of coolant accidents because of the two or more independent cooling circuits in which the fertile material (molten uranium chloride) plays the role of coolant. A very high efficiency aluminum- chloride secondary coolant and turbine working agent is proposed. Together with a district heating system practically no thermal pollution occurs. (auth)
- Research Organization:
- Eidgenoessisches Inst. fuer Reaktorforschung, Wuerenlingen (Switzerland)
- Sponsoring Organization:
- Sponsor not identified
- NSA Number:
- NSA-29-023499
- OSTI ID:
- 4938199
- Report Number(s):
- EIR--249
- Country of Publication:
- Switzerland
- Language:
- English
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