Current status of design and analysis of Korean Helium-Cooled Solid Breeder Test Blanket Module

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It is known that the rest of the capability of tritium self-sufficiency and the extraction of high-grade heat using tritium breeding blanket concepts is one of the major ITER missions. This requires the development of test blanket modules based on a corresponding DEMO blanket design, despite the differences operating conditions between DEMO and ITER. Two blanket concepts such as a Helium-Cooled Solid Breeder (HCSB) blanket and a Helium-Cooled Molten Lithium (HCML) blanket are being considered as Korean Test Blanket Module (TBM) for ITER with the aim for verifying the capability of the breeding blanket design and manufacturability. In this paper, the Current status of the design and analysis for the HCSB TBM is described, The key features of the design include the use of graphite neutron reflectors to reduce the amount of beryllium multiplier. Major analyses have been executed in order to optimize the design. The results of nuclear and thermo-hydraulic analysis show that the design parameters and requirements are satisfied. Also, the safety analysis results show that the design of the TBM system is sufficient to endure several accident events. (C) 2008 Elsevier B.V. All rights reserved.
Publisher
ELSEVIER SCIENCE SA
Issue Date
2008-12
Language
English
Article Type
Article; Proceedings Paper
Citation

FUSION ENGINEERING AND DESIGN, v.83, no.7-9, pp.1163 - 1168

ISSN
0920-3796
URI
http://hdl.handle.net/10203/92372
Appears in Collection
NE-Journal Papers(저널논문)
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