Key technologies of manufacturing and testing for the ITER blanket shield block

被引:0
作者
Kim, Sa-Woong [1 ]
Chung, Si -Kun [1 ]
Chang, Jun -Sung [1 ]
Kim, Duck -Hoi [2 ]
Kim, Hyun-Soo [1 ]
Lee, Hyeon-Gon [1 ]
Jung, Ki-Jung [1 ]
机构
[1] Korea Inst Fus Energy, ITER Korea Domest Agcy, Daejeon, South Korea
[2] ITER Org, Internal Components Div, St Paul Les Durance, France
基金
新加坡国家研究基金会;
关键词
ITER; Blanket shield block; Procurement arrangement; KODA;
D O I
10.1016/j.fusengdes.2024.114371
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
The SB is one of the main in-vessel components manufactured with SS316L(N)-IG to play a major role in neutron shielding, to support the FW panels and to supply the FW panel with cooling water. Cooling channels are located inside of the SB to remove the neutron heat deposition while keeping the structure temperature to acceptable levels. The water coolant is routed first through the plasma-facing first wall panel which is attached to the SB and then through the SB. A number of deep slits are introduced into the SB to disrupt eddy current loops and reduce the Electro-Magnetic (EM) loads on the support system and VV. Water headers are machined on the side of the module with 7-10 mm welded cover plates. A Procurement Arrangements (PAs) for the manufacturing and testing of the SBs have been signed with Korea (50 %) and China (50 %). As part of the PA in Korean Domestic Agency (KODA), Process Qualification (PQ) to ensure the manufacturing and testing ability of the SB was completed successfully through manufacture of a Full Scale Prototype (FSP) as an essential step before starting series production. This paper reports key technologies, such as machining, welding, NDE and hot helium leak testing, of manufacturing and testing for the ITER SB series production in Korea toward successful completion of the missions.
引用
收藏
页数:5
相关论文
共 5 条
  • [1] Construction of hot helium leak test facility for ITER blanket shield block
    Chang, Jun -sung
    Kim, Sa-woong
    Chung, Si-kun
    Nam, Kwan-woo
    Kim, Duck-Hoi
    Kim, Hyun-Soo
    Lee, Hyeon-Gon
    Jung, Ki-Jung
    [J]. FUSION ENGINEERING AND DESIGN, 2023, 193
  • [2] Current status of final design and R&D for ITER blanket shield blocks in Korea
    Ha, M. S.
    Kim, S. W.
    Jung, H. C.
    Hwang, H. S.
    Heo, Y. G.
    Kim, D. H.
    Ahn, H. J.
    Lee, H. G.
    Jung, K. J.
    [J]. NUCLEAR FUSION, 2015, 55 (07)
  • [3] STATUS OF DESIGN AND R&D FOR ITER BLANKET IN KOREA
    Kim, Duck-Hoi
    Kim, Suk-Kwon
    Kim, Sawoong
    Lee, Dong-Won
    Jung, Hun-Chea
    Ahn, Hee-Jae
    Lee, Hyeon Gon
    Jung, Ki-Jung
    [J]. FUSION SCIENCE AND TECHNOLOGY, 2013, 64 (02) : 126 - 130
  • [4] Manufacturing and testing of full scale prototype for ITER blanket shield block
    Kim, Sa-Woong
    Kim, Duck-Hoi
    Jung, Hun-Chea
    Lee, Sung-Ki
    Kang, Sung-Chan
    Zhang, Fu
    Kim, Byoung-Yoon
    Ahn, Hee-Jae
    Lee, Hyeon-Gon
    Jung, Ki-Jung
    [J]. FUSION ENGINEERING AND DESIGN, 2015, 93 : 69 - 75
  • [5] Fabrication and characteristic of the 316L(N)-IG forged block and rolled plate for application to ITER blanket shield block
    Shim, Hee-Jin
    Kim, Sawoong
    Park, ByeongIl
    Kim, Duck-Hoi
    Johansson, Volker
    [J]. FUSION ENGINEERING AND DESIGN, 2020, 156