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核聚变与等离子体物理 ›› 2011, Vol. 31 ›› Issue (2): 161-166.

• 核聚变工程技术 • 上一篇    下一篇

ITER屏蔽包层最新设计的热工水力和热应力分析

康伟山,张秀杰,袁 涛,谌继明   

  1. (核工业西南物理研究院,成都 610041)
  • 收稿日期:2010-10-13 修回日期:2011-02-17 出版日期:2011-06-15 发布日期:2011-09-02
  • 作者简介:康伟山(1977-),男,福建泉州人,硕士,副研究员,主要从事聚变堆包层技术研究。

Thermal-hydraulic and thermo-mechanical analyses of current ITER shield blanket design

KANG Wei-shan, ZHANG Xiu-jie, YUAN Tao, CHEN Ji-ming   

  1. (Southwestern Institute of Physics, Chengdu 610064)
  • Received:2010-10-13 Revised:2011-02-17 Online:2011-06-15 Published:2011-09-02

摘要:

介绍了屏蔽包层最新的设计方案,对比了2004年DDD设计方案与新方案在第一壁和屏蔽块结构上的差别,并对第8号包层模块的屏蔽块进行了热工水力和热应力的分析。结果表明,第8号包层模块屏蔽块的最高温度不超过200ºC,最大Von-Mise应力在200MPa以内,基本满足ITER设计要求,但冷却剂压降稍微偏大,达到0.44MPa。另外,在屏蔽块前端暴露在等离子体表面热负荷的部位,根据热应力分析计算结果,对其承载热负荷能力进行评估,改进了设计方案。

关键词: ITER, 屏蔽包层, 设计, 热工水力分析, 热应力分析

Abstract:

The current design of ITER shield blanket is introduced, and much attention is paid to the comparison between 2004 DDD design and the current design in the structure of first wall and shield block. Besides, the thermal-hydraulic analyses and thermo-mechanical analyses of shield block of No.8 blanket module was performed. The results of analyses indicate that the maximum temperature of No.8 blanket module is below 200ºC and its maximum Von-Mise stress is less than 200MPa, thus the current design of the shield block satisfies with the ITER related requirements, except that the pressure drop is a little bit large, coming up to 0.44MPa. Moreover, the uncovered shield block frontal surface exposed to plasmas heat flux was studied, and its ability of the loaded heat flux was evaluated and optimized based on the result of thermo-mechanical analysis to get a reasonable design pattern.

Key words: ITER, Shield Blanket, Design, Thermal-hydraulic analysis, Thermo-mechanical analysis

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