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Comparison of Coolant Conditions in the Blanket for a Water-Cooled DEMO Reactor SlimCS

Youji SOMEYA, Kenji TOBITA, Hiroyasu UTOH, Haruhiko TAKASE, Changle LIU and Nobuyuki ASAKURA

Japan Atomic Energy Agency, 2-116 Oaza-Obuchi-Aza-Omotedate, Rokkasho, Aomori 039-3212, Japan

(Received 7 December 2010 / Accepted 27 April 2011 / Published 27 July 2011)

Abstract

The blanket structure of the SlimCS has been studied under coolant condition of Pressurized Water Reactor (PWR) to improve the compatibility with F82 H. The neutronic and thermal calculation are performed for the simplified blanket structure, which Li₄SiO₄ pebbles or Li₂O pebbles for tritium breeding and Be₁₂Ti pebbles for neutron multiplication are mixed and these pebbles are filled in the blanket. As a result, the TBR of blanket by PWR water condition is higher than those of sub-critical water condition because the tritium breeding area in the blanket is extended by decreasing thickness of coolant tube in comparison with sub-critical water condition. The blanket with PWR water condition can attain target of the net TBR (≥ 1.05) and satisfy condition of conducting shell for MHD stability.

Copyright (c) 2011 The Japan Society of Plasma Science and Nuclear Fusion Research

Keywords

mixed pebble beds blanket, DEMO, SlimCS, neutronics, thermal analysis, PWR water condition

DOI: 10.1585/pfr.6.2405108

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References

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This paper may be cited as follows:

Youji SOMEYA, Kenji TOBITA, Hiroyasu UTOH, Haruhiko TAKASE, Changle LIU and Nobuyuki ASAKURA, Plasma Fusion Res. 6, 2405108 (2011).