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ITER中国液态锂铅实验回路中的氚技术 被引量:3

Chinese Tritium Technology of the Liquid Lithium-lead Alloy Experimental Loop for ITER
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摘要 多方合作的国际热核实验堆(ITER)计划是全球能源问题关注的一个重要进展标志,中国参与提出的双功能液态锂铅包层模块(DFLL-TBM)是一重要组成部分,采用液态锂铅合金作为氚增殖剂和冷却剂,氢-氦混合气鼓泡方式提取氚。因此,氚技术成为关系液态金属包层成败的关键问题之一。结合中国液态锂铅实验包层技术的发展战略,从理论分析与计算、实验研究和工程设计3方面,阐述了自2004年以来ITER中国液态锂铅回路中的氚技术研究进展。系统介绍了液态锂铅鼓泡器的模拟-设计与研制、锂铅回路中氚的衡算-分析与防氚渗透涂层的进展、锂铅材料辐照-释氚行为的计算与实验、包层氚提取系统的设计等情况。这些工作结果表明,彻底克服锂铅中氚溶解度极低、长期连续操作、磁流体效应(MHD)累积、材料腐蚀等困难,解决氚的滞留、渗透与回收技术难题,降低环境污染是完全可行的。 The multinational cooperation in the International Thermonuclear Experimental Reactor(ITER) plan aims to show that fusion reactors are a new and viable way to address global energy concerns.The Chinese Dual Function Lithium Lead Testing Blanket Module(DFLL-TBM) is one of the major research programs and uses liquid lithium-lead as both breeder and cooler,and a helium-hydrogen gas bubbling method is used to extract tritium.So,tritium technology is a key issue in the liquid metal blanket.Based on the development strategy for Chinese liquid lithium-lead experimental blanket technology,development of Chinese tritium technology for liquid lithium-lead loops between 2004 and 2010 was elaborated in three fields,namely,theoretical analysis and calculation,experimental research,and engineering design.Some important information were introduced,such as the simulation-design-develop of liquid lithium-lead bubbler,tritium analysis and permeation barriers in the loops,tritium release from lithium-lead after irradiation,design of tritium extraction system for the blanket,etc.These works indicate that it is possible to completely overcome the difficulties involving very small solubility of tritium in the lithium-lead,accumulation of Magneto-Hydro-Dynamics(MHD) after a long period of continuous operation,materials corrosion together with the pressure drop caused by wall stress,and many technical problems,such as tritium retention,penetration,recovery and environment pollution,can be thoroughly solved.
出处 《科技导报》 CAS CSCD 北大核心 2011年第5期69-73,共5页 Science & Technology Review
基金 国际热核聚变实验堆(ITER)计划专项2009年度国内配套研究项目(2009GB109006)
关键词 锂铅 包层 提取 回路 lithium-lead tritium blanket extraction loop
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