Numerical Study of High Heat Flux Performances of Flat-Tile Divertor Mock-ups with Hypervapotron Cooling Concept

CHEN Lei (陈蕾); LIU Xiang (刘翔); LIAN Youyun (练友运); CAI Laizhong (才来中)

doi:10.1088/1009-0630/17/9/12

Plasma Science and Technology > 2015 > 17(9): 792-796. > DOI: 10.1088/1009-0630/17/9/12

CHEN Lei (陈蕾), LIU Xiang (刘翔), LIAN Youyun (练友运), CAI Laizhong (才来中). Numerical Study of High Heat Flux Performances of Flat-Tile Divertor Mock-ups with Hypervapotron Cooling Concept[J]. Plasma Science and Technology, 2015, 17(9): 792-796. DOI: 10.1088/1009-0630/17/9/12

Citation:

PDF (335 KB)

Numerical Study of High Heat Flux Performances of Flat-Tile Divertor Mock-ups with Hypervapotron Cooling Concept

Southwestern Institute of Physics, Chengdu 610041, China

Funds: supported by the National Magnetic Confinement Fusion Science Program of China (Nos. 2011GB110001 and 2011GB110004)

More Information

Received Date: October 09, 2014

Graphical Abstract

Abstract

Abstract

The hypervapotron (HV), as an enhanced heat transfer technique, will be used for ITER divertor components in the dome region as well as the enhanced heat flux first wall panels. W-Cu brazing technology has been developed at SWIP (Southwestern Institute of Physics), and one W/CuCrZr/316LN component of 450 mm×52 mm×166 mm with HV cooling channels will be fabricated for high heat flux (HHF) tests. Before that a relevant analysis was carried out to optimize the structure of divertor component elements. ANSYS-CFX was used in CFD analysis and ABAQUS was adopted for thermal–mechanical calculations. Commercial code FE-SAFE was adopted to compute the fatigue life of the component. The tile size, thickness of tungsten tiles and the slit width among tungsten tiles were optimized and its HHF performances under International Thermonuclear Experimental Reactor (ITER) loading conditions were simulated. One brand new tokamak HL-2M with advanced divertor con?guration is under construction in SWIP, where ITER-like ?at-tile divertor components are adopted. This optimized design is expected to supply valuable data for HL-2M tokamak.
- divertor components,
- hypervapotron cooling channels,
- heat transfer,
- fatigue life

FullText(HTML)

References (17)

References

1 Baxi C B. 1995, Comparison of Swirl Tube and Hypervapotron for Cooling of ITER Divertor. 16 th IEEE/NPSS Symposium, Urbana-Champaign

2 Escourbiac F, Bobin-Vastra I, Kuznetsov V, et al.2005, Fusion Eng. Des., 75-79: 387

3 Escourbiac F, Schlosser J, Merola M, et al. 2003, Fusion Eng. Des., 66-68: 30

4 Litunovsky N, Alekseenko E, Makhankov A, et al.2011, Fusion Eng. Des., 86: 1749

5 Bolt H, Barabash V, Krauss W, et al. 2004, J. Nucl.Mater., 329-333: 66

6 Escourbiac F, Merola M, Raffray R, et al. 2013, Design Development of a Full W Divertor for ITER. 16 th ICFRM, Beijing, China

7 Chen L, Lian Y, Liu X. 2014, Plasma Science and Technology, 16: 278

8 Lian Y, Liu X, Xu Z, et al. 2013, Fusion Eng. Des., 88:1696

9 Li Q, Qin S, Wang W, et al. 2013, Fusion Eng. Des.,88: 1810

10 Zhang X, Chen J, Kang W, et al. 2011, Fusion Eng.Des., 86: 312

11 Liu X, Lian Y, Feng F, et al. 2015, A 400 kW electron beam heat loading facility and the development of divertor components for HL-2M tokamak. 15 th PFMC,Aix-Provence, France

12 Kwon T, Choi C, Song C, et al. 2003, Nuclear Engineering and Design, 226: 260

13 ITER Material Properties Handbook, Document No.S 74 MA 2

14 B H Oh. 1991, Materials Journal, 88: 41

15 Wei Q, Ligda J P, Schuster B E, et al. 2006, Acta Material, 54: 346

16 Holzwarth U, Pisoni M, Scholz R, et al. 2000, J. Nucl. Mater., 279: 19

17 Chen J, Liu X, Wu J, et al. 2008, ITER First Wall Fabrication Technology in China. 2 nd IAEA FEC Geneva, Switzerland

[1]	Mingxiang LU, Le HAN, Qi ZHAO, Juncheng QIU, Jianhong ZHOU, Dinghua HU, Nanyu MOU, Xuemei CHEN. Microchannel cooling technique for dissipating high heat flux on W/Cu flat-type mock-up for EAST divertor[J]. Plasma Science and Technology, 2022, 24(9): 095602. DOI: 10.1088/2058-6272/ac684c
[2]	Lei LI (李磊), Le HAN (韩乐), Pengfei ZI (訾鹏飞), Lei CAO (曹磊), Tiejun XU (许铁军), Nanyu MOU (牟南瑜), Zhaoliang WANG (王兆亮), Lei YIN (殷磊), Damao YAO (姚达毛). Conceptual design and heat transfer performance of a flat-tile water-cooled divertor target[J]. Plasma Science and Technology, 2021, 23(9): 95601-095601. DOI: 10.1088/2058-6272/ac0689
[3]	ZHANG Jingyang (张镜洋), HAN Le (韩乐), CHANG Haiping (常海萍), LIU Nan (刘楠), XU Tiejun (许铁军). The Corrected Simulation Method of Critical Heat Flux Prediction for Water-Cooled Divertor Based on Euler Homogeneous Model[J]. Plasma Science and Technology, 2016, 18(2): 190-196. DOI: 10.1088/1009-0630/18/2/16
[4]	LIAN Youyun (练友运), LIU Xiang (刘翔), FENG Fan (封范), CHEN Lei (陈蕾), CHENG Zhengkui (程正奎), WANG Jin (王金), CHEN Jiming (谌继明). Manufacturing and High Heat Flux Testing of Brazed Flat-Type W/CuCrZr Plasma Facing Components[J]. Plasma Science and Technology, 2016, 18(2): 184-189. DOI: 10.1088/1009-0630/18/2/15
[5]	HAN Le (韩乐), CHANG Haiping (常海萍), ZHANG Jingyang (张镜洋), XU Tiejun (许铁军). Numerical Simulation on Subcooled Boiling Heat Transfer Characteristics of Water-Cooled W/Cu Divertors[J]. Plasma Science and Technology, 2015, 17(4): 347-352. DOI: 10.1088/1009-0630/17/4/16
[6]	YU Jianyang (俞建阳), CHEN Fu (陈浮), LIU Huaping (刘华坪), SONG Yanping (宋彦萍). Numerical Study of Fluid Dynamics and Heat Transfer Induced by Plasma Discharges[J]. Plasma Science and Technology, 2015, 17(1): 41-49. DOI: 10.1088/1009-0630/17/1/09
[7]	CAO Chengzhi(曹诚志), LIU Dequan(刘德权), LIN Tao(林涛), QIAO Tao(乔涛). Investigation on the Fatigue Characteristic in Support Structure of HL-2M Tokamak[J]. Plasma Science and Technology, 2014, 16(2): 172-176. DOI: 10.1088/1009-0630/16/2/15
[8]	GAO Yu(高宇), GAN Kaifu(甘开福), GONG Xianzu(龚先祖), GAO Xiang(高翔), LIANG Yunfeng(梁云峰), EAST Team. Study of Striated Heat Flux on EAST Divertor Plates Induced by LHW Using Infrared Camera[J]. Plasma Science and Technology, 2014, 16(2): 93-98. DOI: 10.1088/1009-0630/16/2/02
[9]	GAO Jinming (高金明), LI Wei (李伟), XIA Zhiwei (夏志伟), PAN Yudong (潘宇东), et al.. Analysis of Divertor Heat Flux with Infrared Thermography During Gas Fuelling in the HL-2A Tokamak[J]. Plasma Science and Technology, 2013, 15(11): 1103-1107. DOI: 10.1088/1009-0630/15/11/05
[10]	WU Cheng (吴诚), PAN Wanjiang (潘皖江). Research and Analysis on Tensile and Compressive Fatigue Performance of Cryogenic Axial Insulation Breaks[J]. Plasma Science and Technology, 2013, 15(7): 716-720. DOI: 10.1088/1009-0630/15/7/20