著者

Michio Yamawaki Yuji Arita Takayuki Terai Tadafumi Koyama Koichi Uozumi Yuma Sekiguchi Masami Taira

出版者

The Japan Society of Mechanical Engineers

雑誌

Proceedings of the ... International Conference on Nuclear Engineering. Book of abstracts : ICONE (ISSN:24242934)

巻号頁・発行日

pp._ICONE23-1, 2015-05-17 (Released:2017-06-19)

被引用文献数

1 1

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Source term for severe accident analysis of molten salt reactors(MSRs) has been investigated as part of preliminary efforts to develop MSRs. As a severe accident of MSRs, exposure of heated fluoride fuel molten salt to atmosphere was assumed to take place. Vaporization of fluoride molten salt was studied by means of the two methods, the Knudsen effusion mass spectrometry as well as the transpiration method. The former was applied to pseudo-binary fluoride systems to clarify the behaviors of cesium and iodine in the fluoride molten salt. The latter was applied to the mixture of CsI and FLiNaK. These experiments were carried out as the first step of the source term studies, so that interaction with air components has not been covered yet. From this study, useful information related to the source term for MSRs have been obtained. This work suggests how to solve the problem to establish the source term for severe accident analysis of MSRs.

著者

Michio Yamawaki Tadafumi Koyama

出版者

The Japan Society of Nuclear and Radiochemical Sciences

雑誌

Journal of Nuclear and Radiochemical Sciences (ISSN:13454749)

巻号頁・発行日

vol.16, pp.1-4, 2016 (Released:2017-04-05)

参考文献数

27

被引用文献数

1 5

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The transmutation methods to reduce the burden of high level radioactive waste had been compared to identify the most suitable method for this purpose. The results showed that the molten salt reactor (MSR) was suggested to be an effective transmutation system. Based on this result, a new concept of Integral Molten Salt Fast Reactor (IMSFR) as a highly efficient transmutation system for transuranium elements has been proposed in this study; the system consists of a combination of an MSR fuelled with chloride molten salt fuel and the chloride-based pyrochemical processing subsystem. In this system MSR fuel can be transferred between the reactor core and the pyrochemical processing subsystem without chemical form change.