Advanced Search+
YANG Hong(杨洪), SONG Yuntao(宋云涛), WANG Zhongwei(王忠伟). Thermal and Hydraulic Analysis of the ITER Upper Vertical Stabilization Coil[J]. Plasma Science and Technology, 2014, 16(7): 706-711. DOI: 10.1088/1009-0630/16/7/13
Citation: YANG Hong(杨洪), SONG Yuntao(宋云涛), WANG Zhongwei(王忠伟). Thermal and Hydraulic Analysis of the ITER Upper Vertical Stabilization Coil[J]. Plasma Science and Technology, 2014, 16(7): 706-711. DOI: 10.1088/1009-0630/16/7/13

Thermal and Hydraulic Analysis of the ITER Upper Vertical Stabilization Coil

More Information
  • Received Date: June 26, 2013
  • The ITER upper vertical stabilization (VS) coil is a part of the ITER in-vessel coil (IVC) system, which has the abilities of restraining edge localized modes (ELMs) and maintaining plasma vertical stability. Preliminary structural analysis of the coil has revealed serious thermal stress problems. Due to the very restricted geometry space, it is necessary to perform detailed analysis on thermal and hydraulic characteristics to help optimal design of the coil. It will focus on the temperature distribution and energy balance, as well as some key factors, such as the coolant flow state and surface emissivity, which have influences on the coil performance. The APDL code and some hand calculations are employed in the analysis. The results show that the coolant convection can effectively take away the heat deposited in the coil. But improving the coolant flow state can hardly mitigate the peak temperature occurring at the edges of coil attachments, which are located far away from the coolant. Thermal radiation was expected to be a good method of cooling down these parts. But the reality is not so optimistic since it usually contributes little in the whole energy balance. However, the effect of thermal radiation will become remarkable when bad scenarios or accidents take place. Poor radiation performance of the coil will result in a potential safety hazard.
  • 1.Neumeyer C, Brooks A, Bryant L, et al. 2011, Fusion Science and Technology, 60: 95
    2 Kalish M, Heitzenroeder P, Brooks A, et al. 2011,ITER In-Vessel Coil design and R&D. IEEE 24th Symposium on Fusion Engineering, Chicago, IL, USA,p.1-6
    3 Humphreys DA, Casper TA, Eidietis N, et al. 2009,Nuclear Fusion, 49: 32
    4 Martin A, Daly E. 2011, Fusion Science and Technology, 60: 653
    5 Rebut P H, Campbell D, Brooks A W, et al. 2009,An Overview of the ITER In-vessel Coil Systems.23rd IEEE/NPSS Symposium on Fusion Engineering SOFE, San Diego, CA, USA, p.1-4
    6 Bohm T D, Sawan M E, Jackson S T, et al. 2012, Fusion Engineering and Design, 87: 657
    7 Villari R, Petrizzi L, Brolatti G, et al. 2011, Fusion Engineering and Design, 86: 584
    8 Ambrosino G, Ariola M, De Tommasi G, et al. 2009,IEEE Transactions on Plasma Science, 37: 1324
  • Related Articles

    [1]Yong LU (卢勇), Lijun CAI (蔡立君), Yuxiang LIU (刘雨祥), Jian LIU (刘健), Yinglong YUAN (袁应龙), Guoyao ZHENG (郑国尧), Dequan LIU (刘德权). Thermal-hydraulic analysis of the HL-2M divertor using an homogeneous equilibrium model[J]. Plasma Science and Technology, 2017, 19(9): 95601-095601. DOI: 10.1088/2058-6272/aa7628
    [2]Shanwen ZHANG (张善文), Yuntao SONG (宋云涛), Linlin TANG (汤淋淋), Zhongwei WANG (王忠伟), Xiang JI (戢翔), Shuangsong DU (杜双松). Electromagnetic–thermal–structural coupling analysis of the ITER edge localized mode coil with fiexible supports[J]. Plasma Science and Technology, 2017, 19(5): 55601-055601. DOI: 10.1088/2058-6272/aa57f4
    [3]Shanwen ZHANG (张善文), Yuntao SONG (宋云涛), Kun LU (陆坤), Zhongwei WANG (王忠伟), Jianfeng ZHANG (张剑峰), Yongfa QIN (秦永法). Thermal analysis of the cryostat feed through for the ITER Tokamak TF feeder[J]. Plasma Science and Technology, 2017, 19(4): 45601-045601. DOI: 10.1088/2058-6272/aa57ec
    [4]CHENG Xiaoman (成晓曼), MA Xuebin (马学斌), JIANG Kecheng (蒋科成), CHEN Lei (陈磊), HUANG Kai (黄凯), LIU Songlin (刘松林). Thermal Hydraulic Design and Analysis of a Water-Cooled Ceramic Breeder Blanket with Superheated Steam for CFETR[J]. Plasma Science and Technology, 2015, 17(9): 787-791. DOI: 10.1088/1009-0630/17/9/11
    [5]ZHANG Shanwen(张善文), SONG Yuntao(宋云涛), WANG Zhongwei(王忠伟), LU Su(卢速), JI Xiang(戢翔), DU Shuangsong(杜双松), LIU Xufeng(刘旭峰), FENG Changle(冯昌乐), YANG Hong(杨洪), WANG Songke(王松可), LUO Zhiren(罗志仁). Rapid Thermal-Hydraulic Analysis and Design Optimization of ITER Upper ELM Coils[J]. Plasma Science and Technology, 2014, 16(10): 978-983. DOI: 10.1088/1009-0630/16/10/14
    [6]ZHANG Shanwen(张善文), SONG Yuntao(宋云涛), WANG Zhongwei(王忠伟), LU Su(卢速), JI Xiang(戢翔), DU Shuangsong(杜双松), LIU Xufeng(刘旭峰), FENG Changle(冯昌乐), YANG Hong(杨洪), WANG Songke(王松可), LUO Zhiren(罗志仁). Mechanical Analysis and Optimization of ITER Upper ELM Coil & Feeder[J]. Plasma Science and Technology, 2014, 16(8): 794-799. DOI: 10.1088/1009-0630/16/8/11
    [7]CEN Yishun (岑义顺), LI Qiang (李强), DING Yonghua (丁永华), CAI Lijun (蔡立君), et al.. Stress and Thermal Analysis of the In-Vessel RMP Coils in HL-2M[J]. Plasma Science and Technology, 2013, 15(9): 939-944. DOI: 10.1088/1009-0630/15/9/20
    [8]LEI Mingzhun (雷明准), SONG Yuntao (宋云涛), DU Shijun (杜世俊), YE Minyou (叶民友), XI Weibin(奚维斌), LIU Xufeng (刘旭峰), LIU Chen (刘辰). Preliminary Thermal Mechanical Analysis of the Equatorial Thermal Shield for ITER[J]. Plasma Science and Technology, 2012, 14(10): 932-635. DOI: 10.1088/1009-0630/14/10/14
    [9]XU Tiejun, HUANG Shenghong, XIE Han, SONG Yuntao, ZHAN Ping, GAO Daming. Optimization of Heat-Sink Cooling Structure in EAST with Hydraulic Expansion Technique[J]. Plasma Science and Technology, 2011, 13(6): 765-768.
    [10]KANG Weishan(康伟山), CHEN Jiming(谌继明), WU Jihong(吴继红). Analysis and Optimization of Cooling Channels in ITER Blanket Module[J]. Plasma Science and Technology, 2010, 12(5): 628-631.

Catalog

    Article views (169) PDF downloads (960) Cited by()

    /

    DownLoad:  Full-Size Img  PowerPoint
    Return
    Return