Flow analysis and test for ITER thermal shield components

被引：2
|
作者：
Nam, Kwanwoo [1 ]
Lim, Kisuk [2 ]
Kang, Dongkwon [1 ]
机构：
[1] NFRI, ITER Korea, Daejeon, South Korea
[2] SFA Engn Corp, Asan, South Korea
来源：
FUSION ENGINEERING AND DESIGN | 2018年 / 136卷
关键词：
Flow analysis; Flow test; Cooling tube; Orifice; Thermal shield; ITER;
D O I：
10.1016/j.fusengdes.2018.04.004
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：
Flow distribution on the piping network of ITER Thermal Shield (TS) is analyzed and orifice installation is suggested for attenuating flow mal-distribution. Flow test is performed for a TS segment to verify the analysis model. Room temperature nitrogen gas passes through the cooling pipe on TS segment with test flow rate which is equivalent to the actual operating condition of TS. Flow rate is controlled by a thermal mass flow controller and pressure drop between the inlet and the outlet of the pipe routing is measured by a differential pressure gauge. Test result is compared with the analysis one to check the validity of the analysis model for the real manufactured TS segment. The flow test is also conducted for the fabricated orifices. The loss coefficient of the orifice is compared with that used in the analysis. The loss coefficient correlation for the fabricated orifices is obtained from the test results.
引用
收藏
页码：752 / 758
页数：7
相关论文
共 50 条
  • [31] <bold>Shield components adopted to the ITER ECRH Upper Launcher</bold>
    Spaeh, P.
    Heidinger, R.
    Kleefeldt, K.
    Serikov, A.
    Strauss, D.
    Henderson, M.
    2007 JOINT 32ND INTERNATIONAL CONFERENCE ON INFRARED AND MILLIMETER WAVES AND 15TH INTERNATIONAL CONFERENCE ON TERAHERTZ ELECTRONICS, VOLS 1 AND 2, 2007, : 784 - +
  • [32] Optimization of the outer support in the ITER lower cryostat thermal shield
    Noh, C. H.
    Chung, W.
    Lim, J.
    Lee, B. C.
    FUSION ENGINEERING AND DESIGN, 2016, 103 : 85 - 92
  • [33] Study on the endoscopic inspection of ITER thermal shield cooling pipes
    Nam, Kwanwoo
    Her, Namil
    Park, Won Woo
    Won, Jong Moon
    Kim, Il Jin
    Kang, Youngkil
    Kang, Dong Kwon
    FUSION ENGINEERING AND DESIGN, 2019, 146 : 1600 - 1604
  • [34] Study on the new manufacture of ITER vacuum vessel thermal shield
    Nam, Kwanwoo
    Kang, Dongkwon
    You, Moohyun
    Kim, Myeongjun
    Kim, Sang-chul
    Noh, Chang Hyun
    Kim, Hyunsoo
    Jung, Kijung
    FUSION ENGINEERING AND DESIGN, 2025, 215
  • [35] Development of silver coating process and facilities for ITER thermal shield
    Kang, D. K.
    Kim, R. G.
    Nam, K.
    Noh, C. H.
    Chung, W.
    Yoon, D. C.
    Lim, K.
    Baek, J. P.
    FUSION ENGINEERING AND DESIGN, 2016, 109 : 817 - 823
  • [36] Computational thermo-fluid exploratory design analysis for complex ITER first wall/shield components
    Youchison, Dennis L.
    Natoni, Greg
    Narula, Manmeet
    Ying, Alice
    FUSION ENGINEERING AND DESIGN, 2008, 83 (7-9) : 1025 - 1033
  • [37] Thermal analysis of the in-vessel components of the ITER plasma-position reflectometry
    Quental, P. B.
    Policarpo, H.
    Luis, R.
    Varela, P.
    REVIEW OF SCIENTIFIC INSTRUMENTS, 2016, 87 (11):
  • [38] 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
  • [39] ITER SHIELD BLOCK COOLING SYSTEM DESIGN AND ANALYSIS
    Kang, Weishan
    Yuan, Tao
    Zhang, Xiujie
    PROCEEDINGS OF THE 21ST INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING - 2013, VOL 5, 2014,
  • [40] Modelling and computer simulation for the manufacture by powder HIPing of blanket shield components for ITER
    Gillia, O.
    Boireau, B.
    Boudot, C.
    Cottin, A.
    Bucci, P.
    Vidotto, F.
    Leibold, J. -M.
    Lorenzetto, P.
    FUSION ENGINEERING AND DESIGN, 2007, 82 (15-24) : 2001 - 2007
12345