Experimental and numerical study of the pressure drop for ITER blanket shield block

被引:1
|
作者
Ha, Min-Su [1 ]
Kim, Sawoong [1 ]
Jung, Hun-Chea [1 ]
Shim, Hee-Jin [1 ]
Ahn, Hee-Jae [1 ]
机构
[1] Natl Fus Res Inst, ITER Korea, Daejeon, South Korea
关键词
Pressure drop; ITER; Blanket shield block; Experiment; CFD analysis; DESIGN;
D O I
10.1016/j.fusengdes.2016.01.047
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 blanket shield block (SB) is located inside the ITER vacuum chamber, and the main function is to provide the thermal and nuclear shielding to the vacuum vessel and external components. The SB is foreseen to undergo a significant heat load which is a body load throughout the whole thickness of the SB under normal operation conditions. Therefore, the cooling configuration in SB should be designed very carefully based on the various experiences. The pressure drop in the cooling design is one of the most important factors to balance a water distribution of overall blanket cooling system. In order to verify the pressure drop characteristic and validate the design methodology of SB, experiment and numerical analysis are performed and compared their results. These results would be a benchmarking of the numerical results with experimental results to assess the gap between calculations and experiments. (C) 2016 Elsevier B.V. All rights reserved.
引用
收藏
页码:947 / 950
页数:4
相关论文
共 50 条
  • [1] Heat transfer study for ITER blanket shield block cooling design
    Kang, Weishan
    Yuan, Tao
    Zhang, Xiujie
    FUSION ENGINEERING AND DESIGN, 2014, 89 (02) : 94 - 98
  • [2] ITER blanket module shield block design and analysis
    Mitin, D.
    Khomyakov, S.
    Razmerov, A.
    Strebkov, Yu.
    FUSION ENGINEERING AND DESIGN, 2008, 83 (7-9) : 1188 - 1198
  • [3] Key technologies of manufacturing and testing for the ITER blanket shield block
    Kim, Sa-Woong
    Chung, Si -Kun
    Chang, Jun -Sung
    Kim, Duck -Hoi
    Kim, Hyun-Soo
    Lee, Hyeon-Gon
    Jung, Ki-Jung
    FUSION ENGINEERING AND DESIGN, 2024, 202
  • [4] Numerical Analyses of Electromagnetic Forces on the ITER Blanket Module Shield Block During Major Disruptions
    康伟山
    袁涛
    孙倩
    吴继红
    谌继明
    Plasma Science and Technology, 2014, 16 (07) : 701 - 705
  • [5] Numerical Analyses of Electromagnetic Forces on the ITER Blanket Module Shield Block During Major Disruptions
    康伟山
    袁涛
    孙倩
    吴继红
    谌继明
    Plasma Science and Technology, 2014, (07) : 701 - 705
  • [6] Numerical Analyses of Electromagnetic Forces on the ITER Blanket Module Shield Block During Major Disruptions
    Kang Weishan
    Yuan Tao
    Sun Qian
    Wu Jihong
    Chen Jiming
    PLASMA SCIENCE & TECHNOLOGY, 2014, 16 (07) : 701 - 705
  • [7] Cooling optimization for preliminary design of ITER blanket shield block
    Kim, Duck-Hoi
    Ha, Min-Su
    Choi, Jong-Woong
    Ahn, Hee-Jae
    Bak, Joo-Shik
    Jung, Ki-Jung
    FUSION ENGINEERING AND DESIGN, 2012, 87 (5-6) : 921 - 926
  • [8] Hot Helium Leak Test of ITER blanket shield block
    Leng, Zhen
    Chen, Jiming
    Wang, Kun
    Wang, Pinghuai
    Xu, Min
    FUSION ENGINEERING AND DESIGN, 2020, 153
  • [9] 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
    FUSION ENGINEERING AND DESIGN, 2015, 93 : 69 - 75
  • [10] Electromagnetic analyses and optimization for slit configuration of ITER blanket shield block
    Kang, Weishan
    Chen, Jiming
    Wu, Jihong
    Niu, Erwu
    FUSION ENGINEERING AND DESIGN, 2016, 109 : 1587 - 1591