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Published May 2008 | Version v1
Miscellaneous

Fabrication and preparation of a high heat flux test with a mock-up for the first wall of the KO HCML TBM

  • 1. Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

Description

Korea has proposed and designed a Helium Cooled Molten Lithium (HCML) Test Blanket Module (TBM) to be tested in the International Thermonuclear Experimental Reactor (ITER). Ferrite Martensite (FM) steel is used as the structural material and Helium is used as a coolant to cool the first wall and breeding zone. Liquid Lithium is circulated for a tritium breeding, not for a cooling purpose. Therefore, the speed of Lithium is very slow up to a few mm/sec. From the performance and safety analyses, the feasibility of this concept has been proven. The FW is an important component which faces the plasma directly and therefore, it is subjected to high heat and neutron loads. The FW is composed of a beryllium (Be) layer as a plasma facing material and Ferrite Martensite Steel (FMS) as a structure material. In order to develop the fabrication technology for a TBM structure, several mock-ups, especially for the first wall channels, were fabricated with a HIP (Hot Isostatic Pressing), which was developed similarly to the development of the ITER blanket FW in Korea. In the present paper, fabrication of a TBM FW mock-up and a high heat flux (HHF) test plan for confirming its integrity are presented

Part of:
Proceedings of the Korean Nuclear Society Spring Meeting

Additional details

Publishing Information

Publisher
KNS
Imprint Place
Daejeon (Korea, Republic of)
Imprint Title
Proceedings of the KNS spring meeting
Imprint Pagination
[1 CD-ROM]
Journal Page Range
[2 p.]

Conference

Title
2008 spring meeting of the KNS
Dates
29-30 May 2008
Place
Kyeongju (Korea, Republic of)

INIS

Country of Publication
Korea, Republic of
Country of Input or Organization
Korea, Republic of
INIS RN
39109351
Subject category
S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
DESIGN; FABRICATION; FEASIBILITY STUDIES; HEAT FLUX; ITER TOKAMAK; MOCKUP; PERFORMANCE; PLASMA; SAFETY ANALYSIS; THERMONUCLEAR REACTORS
Descriptors DEC
CLOSED PLASMA DEVICES; STRUCTURAL MODELS; THERMONUCLEAR DEVICES; THERMONUCLEAR REACTORS; TOKAMAK DEVICES; TOKAMAK TYPE REACTORS

Optional Information

Notes
4 refs, 5 figs