Fast Reactors and Accelerator Driven Systems Knowledge Base

Conference Article: Thorium cycle implementation through plutonium incineration by thorium molten-salt nuclear energy synergetics

Furukawa, K. (International Thorium Molten-Salt Forum, Oiso (Japan)); Simonenko, V. (Institute of Technical Physics, Snezhinks (Russian Federation)); Mitachi, K. (Toyohashi University of Technology, Toyohashi, Aichi (Japan)); Furuhashi, A. (Nuclear Material Control Center, Tokyo (Japan)); Yoshioka, R. (Toshiba Inc., Yokohama (Japan)); Chigrinov, S. (Radiation Physics and Chemistry Problems Institute, Minsk (Belarus)); Lecocq, A. (EURIWA, Orsay (France)); Kato, Y. (Japan Atomic Energy Research Institute, Tokai (Japan))

Abstract

Considering the increasing world energy demand and the urgent necessity of replacement of fossil-fuel by nuclear energy for survival of the global environmental crisis, we urgently need to prepare a more rational and a huge nuclear industry. As an improved alternative of present technology, the utilization of U is strongly recommended. ORNL proposed an idealistic MSBR since 1970. We modified it to the world-wide applicable system: THORIMS-NES [Thorium Molten-Salt Nuclear Energy Synergetic System], which is composed of simple thermal fission power stations (FUJI) and fissile-producing Accelerator Molten-Salt Breeder (AMSB). FUJI is a size-flexible NEAR BREEDER even not using continuous chemical processing and core-graphite exchange, and AMSB is based on a single-fluid molten-salt target/blanket concept, the technological development of which is easy and simple except for the high-current proton accelerator. THORIMS-NES has many advantages, and here the issues of safety, nuclear-proliferation and social/philosophical acceptance is mostly explained. In practice, the shift to THORIMS-NES from the present U-Pu cycle era will be smoothly implemented by converting Pu and TRU in weapons and spent-fuels into molten fluoride salt by a drying process (such as the Russian FREGATE project) which was established by the French, Russians and Czechs. Pilot plant 'mini FUJI', 7MW(e) might be commissioned after 7 years depending on the result of successful 4 years operation of MSRE in ORNL, and Small Demonstration Reactor 'FUJI-Pu', 150MW(e) can probably be in operation 12 years from now utilizing the world ability of Na-Reactor Technology. Depending on such MSR-technology development, AMSB-Pu might be able to industrialize 20 years from now.

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key words: burnup; design basis accidents; energy policy; lmfbr type reactors; molten salt fueled reactors; plutonium; reactor safety; spent fuels; thorium cycle; uranium 233
Reference:
Proceedings of three IAEA meetings held in Vienna in 1997, 1998 and 1999
International Atomic Energy Agency, Vienna (Austria)
IAEA-TECDOC--1319, pp:123-128