Effect of heat flux and liquid lithium velocity on temperature distribution of free flow of liquid lithium

NUCLEAR FUSION AND PLASMA PHYSICS ›› 2015, Vol. 35 ›› Issue (2): 163-169.

• Nuclear Fusion Engineering and Technology • Previous Articles Next Articles

Effect of heat flux and liquid lithium velocity on temperature distribution of free flow of liquid lithium

ZHU Zhi-chuan1, ZHANG Chuan-wu1, GOU Fu-jun2, WANG Jian-qiang2,YANG Dang-xiao3, MIAO Feng1

(1. College of Electrical and Information Engineering, Southwest University for Nationalities, Chengdu 610041; 2. Institute of Nuclear Science and Technology, Sichuan University, Chengdu 610064; 3. College of Physical Science and Technology, Sichuan University, Chengdu 610064)

Online:2015-06-15 Published:2015-06-15

热通量和液态锂流速对自由流动液态锂温度分布的影响

朱志川1，张传武1，芶富均2，王建强2，杨党校3，苗峰*1

(1. 西南民族大学电气信息工程学院，成都 610041；2. 四川大学原子核科学技术研究所，成都 610064； 3. 四川大学物理科学与技术学院，成都 610064)

作者简介:朱志川(1989-)，男，安徽宿州人，硕士研究生，主要从事等离子体与材料表面相互作用研究。
基金资助:
国家磁约束核聚变能发展研究专项(2013GB114003)；国家自然科学基金(11275135)

Abstract

Abstract:

Commercial software ANSYS CFX are used to calculate the effect of heat flux and liquid lithium velocity on temperature distribution of the free flow of liquid lithium. The calculated results show that the temperature of liquid lithium is higher near the center of guiding groove, the temperature of liquid lithium is lowest in the location corresponding to inlet and outlet of cooling water. The outlet temperature of liquid lithium rises linearly with the increase of plasma heat flux. When the velocity of cooling water is 1.5m·s⁻¹, heat flux are 0.1MW·m⁻² and 1MW·m⁻² respectively, the corresponding temperature of liquid lithium at outlet are 255.3°C and 458.6°C. The temperature of liquid lithium within guiding groove dropped gradually with increase of velocity of liquid lithium, but the amplitude of temperature variation is smaller.

Key words: Liquid lithium, Plasma, Heat flux, Temperature distribution

摘要：

应用商业软件ANSYS CFX 计算了等离子体热通量和液态锂流速对自由流动液态锂温度分布的影响。计算结果表明，导向槽中心附近液态锂温度较高，冷却水入口和出口对应位置液态锂温度最低。液态锂出口温度随着等离子体热通量的增大而线性升高，冷却水流速为1.5m·s⁻¹，热通量分别为0.1MW·m⁻² 和1MW·m⁻² 时，液态锂在出口处对应的温度分别为255.3°C 和458.6°C。增大液态锂流速，导向槽内液态锂的温度逐渐降低，但温度变化的幅度较小。计算结果对液态锂回路安全稳定运行提供了一定参考。

关键词: 液态锂, 等离子体, 热通量, 温度分布

CLC Number:

TL333

ZHU Zhi-chuan1, ZHANG Chuan-wu1, GOU Fu-jun2, WANG Jian-qiang2,YANG Dang-xiao3, MIAO Feng1. Effect of heat flux and liquid lithium velocity on temperature distribution of free flow of liquid lithium[J]. NUCLEAR FUSION AND PLASMA PHYSICS, 2015, 35(2): 163-169.

朱志川，张传武，芶富均，王建强，杨党校，苗峰. 热通量和液态锂流速对自由流动液态锂温度分布的影响[J]. 核聚变与等离子体物理, 2015, 35(2): 163-169.

References

[1] Martin G, Lipa M. Li3: first step studies of a liquid lithium limiter [J]. Fusion Engineering and Design, 2002,61−62: 237−243.
[2] Igor E L, Alexey V V. Experience and technical issues of liquid lithium application as plasma facing material in tokamaks [J]. Fusion Engineering and Design, 2010, 85:924−929.
[3] 邓柏权, 黄锦华, 严建成. 流动液态锂第一壁的物理可行性研究[R]. 北京: 中国核科技报告, 2002, 66−70.
[4] 邓柏权, 黄锦华, 彭利林, 等. 聚变堆包层流动锂液帘与堆芯兼容性评估[J]. 核聚变与等离子体物理, 2003,23(3): 170−175.
[5] Whyte D G, Evans T E, Wong C P, et al. Experimental observations of lithium as a plasma-facing surface in the DIII-D tokamak divertor [J]. Fusion Engineering and Design, 2004, 72: 133−147.
[6] Majeski R, Boaz M, Hoffman D, et al. CDX-U operation with a large area liquid lithium limiter [J]. J. Nucl. Mater.,2003, 313−316: 625−629.
[7] Robert Kaita, Laura Berzak, Dennis Boyle, et al.Experiments with liquid metal walls: status of the lithium tokamak experiment [J]. Fusion Engineering and Design,2010, 85: 874−881.
[8] 康伟山, 潘传杰, 许增裕. 液态金属自由表面在聚变堆中的运用研究 [J]. 科学技术与工程, 2006, 6(6):731−738.
[9] 张秀杰, 许增裕, 潘传杰, 等. 液态金属自由表面膜流MHD 效应的数值模拟[J]. 核聚变与等离子体物理,2008, 28(1): 28−33.
[10] 袁涛, 邓伯权, 陈志, 等. ITER 第一壁、偏滤器靶板和壁的热负荷计算[J]. 科学技术与工程, 2004, 4(9):772−774.
[11] 许增裕, 潘传杰, 张秀杰. 简化理论研究液态包层通道插件流体MHD 效应[J]. 核聚变与等离子体物理,2008, 28(3): 205−208.
[12] 邓柏权, 严建成, 黄锦华. 自由表面液态锂偏滤器靶板物理过程研究[J]. 核科学与工程, 2000, 20(4):373−378.
[13] Brooks J N, Rognlien T D, Ruzic D N, et al.Erosion/redeposition analysis of lithium-based liquid surface divertors [J]. J. Nucl. Mater., 2001, 290−293:185−190.
[14] Allain J P, Nieto M, Coventry M D, et al. Studies of liquid-metal erosion and free surface flowing liquid lithium retention of helium at the University of Illinois[J]. Fusion Engineering and Design, 2004, 72: 93−110.
[15] 唐婵, 王红艳, 裘浔隽, 等. 准静态液态金属锂铅在SLL 包层中的流动换热[J]. 核技术, 2013, 36(11):41−45.
[16] Khripunov B I, Petrov V B, Shapkin V V, et al.Experimental study of lithium target under high power load [J]. J. Nucl. Mater., 2001, 290−293: 201−205.

Effect of heat flux and liquid lithium velocity on temperature distribution of free flow of liquid lithium

热通量和液态锂流速对自由流动液态锂温度分布的影响

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