Preliminary safety analysis of Korea Helium Cooled Solid Breeder Test Blanket Module

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ITER Test Blanket Module (TBM) which will be the act-alike module Corresponding to DEMO blanket is aimed to verify the capability of tritium self-sufficiency and the extraction of high heat using tritium breeding concepts for ITER missions. Conceptual design of Korea Helium-Cooled Solid Breeder (HCSB) TBM, one of two concepts that Korea has proposed, has been performed including performance analyses. In this paper, the results of preliminary safety analyses of Korea HCSB TBM are described. In-vessel, in-box and ex-vessel loss of coolant accidents are selected as three reference accidental scenarios for the TBM. Each scenario is modeled and computed by RELAP5/MOD3.2, developed for thermo-hydraulic transient simulation of light water reactor coolant systems. The results show the robustness of the design from the safety perspective. (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.10-12, pp.1753 - 1758

ISSN
0920-3796
URI
http://hdl.handle.net/10203/92375
Appears in Collection
NE-Journal Papers(저널논문)
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