Fast Reactors and Accelerator Driven Systems Knowledge Base

Conference Article: Molten salt reactor benchmark problem to constrain plutonium

Hirakawa, N.; Aboanber, A.I. (Tohoku University, Sendai (Japan)); Mitachi, K. (Toyohashi University of Technology, Toyohashi (Japan)); Misawa, T. (Kyoto University (Japan))

Abstract

A molten salt reactor (MSR) based on 233U-Th cycle has a positive feature from the standpoint of neutron economy, and it has been studied in Japan to utilize the MSR for the incineration of minor actinides (MA) produced in light water reactors (LWR). Therefore, Japan has proposed to study a MSR in the frame of the IAEA co-ordinated research project on the 'Potential of thorium-based Fuel Cycles to Constrain Plutonium and to Reduce Long-term Waste Toxicities'. It is important to study the basic character of the reactor with simple model especially for the purpose of comparison with other type of reactors. This report presents the results of the benchmark calculation and the effect of fuel volume ratio for the burnup characteristics.

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key words: benchmarks; burnup; flibe; integral cross sections; msre reactor; plutonium fluorides; plutonium; thorium cycle; thorium fluorides

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Reference:

Proceedings of three IAEA meetings held in Vienna in 1997, 1998 and 1999

International Atomic Energy Agency, Vienna (Austria)

IAEA-TECDOC--1319, pp:198-206