期刊文献+

CFETR COOL包层热-机械性能研究 被引量:1

Thermal-mechanic Analysis on COOL Blanket for CFETR
原文传递
导出
摘要 超临界二氧化碳(sCO_(2))液态锂铅包层(COOL)是中国聚变工程实验堆(CFETR)的候选包层,其主要功能是增殖产氚、屏蔽中子辐射以及能量转换发电。COOL包层在正常运行工况下需要承受冷却剂压力、热应力、重力、电磁力等载荷。本文在不考虑重力和电磁载荷的情况下,采用ANSYS有限元方法对COOL包层扇段的赤道面外包层模块进行热-机械性能分析,结果表明,COOL包层在正常运行工况下,各类材料的最高温度不超过限值,并且结构应力能够满足ITER SDC-IC设计标准,分析结果可为包层优化设计提供重要参考和数据支撑。 The supercritical carbon dioxide(sCO_(2)) liquid lead-lithium blanket(COOL) is a candidate for China Fusion Engineering Test Reactor(CFETR),and its main functions are tritium breeding,neutron radiation shielding and energy conversion to generate electricity.COOL cladding needs to bear loads such as coolant pressure,thermal stress,gravity and electromagnetic force under normal operating conditions.In this paper,the thermal and mechanical performance of the equatorial outboard blanket module in the COOL blanket segment are analyzed by ANSYS finite element method.The results show that the maximum temperature of various materials of the blanket under normal operating condition does not exceed the upper limit,and the structural stress could meet the ITER SDC-IC design standard.The analysis results can provide important reference and data support for the following iterative optimal design of the blanket.
作者 蒋科成 余毅 马学斌 陈磊 刘松林 Jiang Kecheng;Yu Yi;Ma Xuebin;Chen Lei;Liu Songlin(Institute of Plasma Physics,Hefei Institutes of Physical Science,Chinese Academy of Sciences,Hefei,230031,China;University of Science and Technology of China,Hefei,230026,China)
出处 《核动力工程》 EI CAS CSCD 北大核心 2023年第S01期101-107,共7页 Nuclear Power Engineering
基金 国家自然科学基金项目(12205330)。
关键词 中国聚变工程实验堆(CFETR) 超临界二氧化碳(sCO_(2))液态锂铅包层(COOL) 热-机械性能 CFETR Supercritical carbon dioxide(sCO_(2))liquid lead-lithium blanket(COOL) Thermal-mechanical properties
  • 相关文献

同被引文献18

引证文献1

相关作者

内容加载中请稍等...

相关机构

内容加载中请稍等...

相关主题

内容加载中请稍等...

浏览历史

内容加载中请稍等...
;
使用帮助 返回顶部