Thermo-mechanical response simulation and analysis of W material under fusion related transient heat flux

doi:10.16568/j.0254-6086.201703011

NUCLEAR FUSION AND PLASMA PHYSICS ›› 2017, Vol. 37 ›› Issue (3): 308-312.DOI: 10.16568/j.0254-6086.201703011

• Nuclear Fusion Engineering and Technology • Previous Articles Next Articles

Thermo-mechanical response simulation and analysis of W material under fusion related transient heat flux

LI Xiang-bin, LI Chang-jun, ZHU Da-huan, CHEN Jun-ling

(1. Institute of Plasma Physics, Chinese Academy of Science, Hefei 230031; 2. China International Nuclear Fusion Energy Program Execution Centre, Beijing 100038; 3. University of Science and Technology of China, Hefei 230026)

Received:2016-08-22 Revised:2017-06-05 Online:2017-09-15 Published:2017-09-14

钨材料在瞬态高热流冲击下热结构响应过程模拟和分析

李向宾1, 2，李长君1, 3，朱大焕*1，陈俊凌1

(1. 中国科学院等离子体物理研究所，合肥 230031； 2. 中国国际核聚变能源计划执行中心，北京 100038； 3. 中国科学技术大学，合肥 230026)

作者简介:李向宾(1984–)，男，河北承德人，博士研究生，从事面对等离子体材料高热负荷性能研究。
基金资助:
国家自然科学基金资助项目(11405209)

Abstract

Abstract:

Thermo-mechanical analysis was performed to simulate the temperature and stress distribution for tungsten material facing plasma under fusion related transient heat flux loading and unloading using finite-element analysis code ANSYS. And combined its mechanical properties, its crack behavior under transient heat flux was analyzed. The results show that the crack thresholds of W are about 200MW•m^–2(~5ms), 460MW•m^–2 (~1ms) and 660 MW•m^–2(~0.5ms) under single heat shot, corresponding to the coincident heat flux factors (14.14~14.75 MW•m^–2•s^1/2).

Key words: Tungsten, Plasma facing material, Finite-element analysis, Transient heat flux, Thermo- mechanical simulation

摘要：

采用有限元分析软件ANSYS模拟了面对等离子体钨材料在聚变瞬态高热流加载和卸载过程中的温度和应力分布以及演化过程，并结合材料力学性能对热冲击开裂行为进行了分析和讨论。结果表明，在瞬态热流下，钨的单次热冲击开裂阈值约200MW•m^–2(~5ms)、460MW•m^–2 (~1ms)和660MW•m^–2(~0.5ms)，其临界热流因子(14.14~14.75MW•m^–2•s^1/2)也基本一致。

关键词: 钨, 面对等离子体材料, 有限元分析, 瞬态热流, 热-结构模拟

CLC Number:

TL62+6

LI Xiang-bin, LI Chang-jun, ZHU Da-huan, CHEN Jun-ling. Thermo-mechanical response simulation and analysis of W material under fusion related transient heat flux[J]. NUCLEAR FUSION AND PLASMA PHYSICS, 2017, 37(3): 308-312.

李向宾1, 2，李长君1, 3，朱大焕*1，陈俊凌1. 钨材料在瞬态高热流冲击下热结构响应过程模拟和分析[J]. 核聚变与等离子体物理, 2017, 37(3): 308-312.

References

[1] Pitts R A, Carpentier S, Escourbiac F, et al. A full tungsten divertor for ITER: Physics issues and design status[J]. J. Nucl. Mater., 2013, 438: S48–S56.

[2] Federici G, Zhitlukhin A, Arkhipov N, et al. Effects of ELMs and disruptions on ITER divertor armour materials[J]. J. Nucl. Mater.,2005, 337–339: 684–690.

[3] Loewenhoff Th, Linke J, Pintsuk G, et al. ITER-W monoblocks under high pulse number transient heat loads at high temperature[J]. J. Nucl. Mater., 2015, 463, 202 –205.

[4] Huber A, Burdakov A, Zlobinski M, et al. Investigation of the impact on tungsten of transient heat loads induced by laser irradiation, electron beams and plasma guns [J]. Transactions of Fusion Science and Technology, 2013, 63: 197–200.

[5] Hirai T, Pintsuk G, Linke J, et al. Cracking failure study of ITER-reference tungsten grade under single pulse thermal shock loads at elevated temperatures[J]. J. Nucl. Mater., 2009, 390–391: 751–754.

[6] Riccardi B, Gavila P, Gliniatulin R, et al. Effect of stationary high heat flux and transient ELMs-like heat loads on the divertor PFCs[J]. Fus. Eng. Des., 2013, 88: 1673–1676.

[7] Arakcheev A S, Huber A, Wirtz M, et al. Theoretical investigation of crack formation in tungsten after heat loads[J]. J. Nucl. Mater., 2015, 463: 246–249.

[8] Dahuan Zhu, Junling Chen. Thermal stress analysis on chemical vapor deposition tungsten coating as plasma facing material for EAST[J]. J. Nucl. Mater., 2014, 455: 185–188.

[9] 薛奎，陈俊凌，朱大焕. ITER偏滤器W/Cu单体模块热-结构模拟与分析[J]. 核聚变与等离子体物理, 2013, 33(4): 354–358.

[10] ITER Joint Central Team. ITER material assessment report[R]. 2001.

[11] Hirai T, Pintsuk G. Thermo-mechanical calculations on operation temperature limits of tungsten as plasma facing material[J]. Fus. Eng. Des., 2007, 82: 389–393.

[12] Xiang Liu, Youyun Lian, Lei Chen, et al., Experimental and numerical simulations of ELM-like transient damage behaviors to different grade tungsten and tungsten alloys
[J]. J. Nucl. Mater., 2015, 463: 166–169.

[13] Muyuan Li, Ewald Werner, Jeong-Ha You, Influence of heat flux loading patterns on the surface cracking features of tungsten armor under ELM-like thermal shocks[J]. J. Nucl. Mater., 2015, 457: 256–265.

[1]	LI Feng, LIU Ming, QIAN Wei, ZHANG Gui-hang, CHE Tong, WEI Ran, CHEN Ji-ming, ZHENG Peng-fei. The influence of polishing and vacuum annealing on the microstructure of tungsten surface [J]. Nuclear Fusion and Plasma Physics, 2024, 44(4): 394-400.
[2]	QU Miao, YAN Sha. Study on dependence of tungsten primary crack on pulse width time under transient heat flow [J]. Nuclear Fusion and Plasma Physics, 2024, 44(2): 206-213.
[3]	QU Miao, YAN Sha. Study on recrystallization of tungsten under transient heat loads [J]. Nuclear Fusion and Plasma Physics, 2024, 44(1): 58-64.
[4]	WANG Bao-guo, , ZHU Da-huan , DING Rui , MU Lei , LI Chang-jun , CHEN Jun-ling. Experimental study of arc induced on tungsten surface in the EAST edge plasma [J]. Nuclear Fusion and Plasma Physics, 2023, 43(2): 156-160.
[5]	HUANG Pan, WANG Yi-ming, CHEN Ji-ming, WANG Ping-huai . Evolution of W/Fe interfacial microstructure and shear performance for W/Fe/RAFM-steel joint in process of normalizing and tempering heat treatment [J]. Nuclear Fusion and Plasma Physics, 2021, 41(3): 240-246.
[6]	WANG Yi-ming, HUANG Pan, CHEN Ji-ming, WANG Ping-huai. Analysis on microstructure and properties of W/Fe/CuCrZr module bonded by HIP technique [J]. NUCLEAR FUSION AND PLASMA PHYSICS, 2021, 41(2): 124-130.
[7]	WANG Yan, , , ZHANG Xi-yang, ZHOU Zi-bo, , YAO Da-mao. Study on cutting first wall tungsten material for fusion reactor by premixed abrasive jet [J]. Nuclear Fusion and Plasma Physics, 2021, 41(1): 85-90.
[8]	QIAN Wei, ZHENG Peng-fei, WANG Lian, XU Li-sha,LIU Xing, WEI Ran, BAI Quan, CHE Tong. Study of early stage surface evolution of molybdenum coated tungsten bombarded by helium plasma [J]. NUCLEAR FUSION AND PLASMA PHYSICS, 2020, 40(2): 142-147.
[9]	LIU Hong-tao, WANG Fu-qiong, ZHONG Fang-chuan. Modeling study on the effects of drifts on tungsten impurity production and transport in EAST [J]. NUCLEAR FUSION AND PLASMA PHYSICS, 2019, 39(4): 289-295.
[10]	XU Hou-chang, LI Lei, YAO Da-mao, ZHOU Zi-bo, CAO Lei, Xu Tie-jun, HAN Le, ZI Peng-fei. Simulation on heat transfer of new type lower divertor in EAST [J]. NUCLEAR FUSION AND PLASMA PHYSICS, 2019, 39(2): 127-133.
[11]	ZHOU Hai-bao, LIU Su-mei, SUN Jin-xin, GUO Liang-liang, XIA Jun-fu, WEI Fei. Experiment and analytical simulation of fatigue properties of TIG welding and electron beam welding of RAFM steel [J]. NUCLEAR FUSION AND PLASMA PHYSICS, 2019, 39(2): 158-164.
[12]	LIU Bai-qi, YANG Juan-cheng, QI Tian-yu, REN Dong-wei, NI Ming-jiu. Experimental study on the lithium film flow in horizontal magnetic fields [J]. NUCLEAR FUSION AND PLASMA PHYSICS, 2019, 39(1): 62-67.
[13]	HU Zhi-qiang, ZHAO Feng-chao, WU Xin-hua, LIAO Hong-bin, WANG Xiao-yu, FENG Kai-ming. A preliminary study of microstructure and properties about CLF-1 steel and 316L TIG welding joint used for fusion reactor [J]. NUCLEAR FUSION AND PLASMA PHYSICS, 2018, 2(4): 446-451.
[14]	MA Xiao-chun, CAO Xiao-gang, CAO Zhi, HAN Lei, XIA Wen-xing, SHU Lei, HE Ping-ni, GUO Fu-jun. Characteristics of helium plasma produced in cascade arc discharge [J]. NUCLEAR FUSION AND PLASMA PHYSICS, 2017, 37(3): 267-273.
[15]	XIAO Xuan, YAO Da-mao, CAO Lei, ZHOU Zi-bo. Thermal hydraulic analysis of EAST W-divertor outer target [J]. NUCLEAR FUSION AND PLASMA PHYSICS, 2015, 35(4): 356-360.

Thermo-mechanical response simulation and analysis of W material under fusion related transient heat flux

钨材料在瞬态高热流冲击下热结构响应过程模拟和分析

PDF

Knowledge

Abstract

Cite this article

share this article

References

Related Articles 15

Recommended Articles

Metrics