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
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