Presentation Information

[2D08]Feasibility Study of Integral Molten Chloride Salt Fast Reactor (V)(4) Nuclear Fuel Cycle Simulation for Molten Salt Fast Reactor

*Masahiko Nakase1, Tomohiro Okamura1, Yohihisa Tahara2, Hiroyasu Motizuki3, Tsuyoshi Murakami4, Tadafumi Koyama4 (1. Science Tokyo, 2. NAIS, 3. BERD, 4. CRIEPI)

Keywords:

Chloride molten salt fast reactors,Nuclear Fuel Cycle Simulation,Introduction scenario,Pyroprocessing,Waste

Research and development of chloride molten salt fast reactors are accelerating worldwide, but there are only a limited number of examples of introduction scenarios and quantitative material quantity evaluation reports. In this study, we have compiled information on the core, reprocessing, and waste that has been examined guided by BERD and carried out a quantity evaluation using NMB 4 code. In this presentation quantity evaluation results and the scenario for introducing chloride molten salt fast reactors will be discussed.

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