聚变堆面向等离子体钨基材料的研究进展

留言板

尊敬的读者、作者、审稿人, 关于本刊的投稿、审稿、编辑和出版的任何问题, 您可以本页添加留言。我们将尽快给您答复。谢谢您的支持!

姓名

邮箱

手机号码

标题

留言内容

验证码

基金项目:

教育部新世纪人才计划(NCET-10-0571)

ITER973项目(2011CB 108005)

国家自然科学基金(51101108)

Research Development of Tungsten-Based Materials Used as Plasma Facing Materials of Fusion Reactor

1. Institute of Nuclear Science and Technology, Sichuan University, Chengdu, 610064, China;
2. Science and Technology on Reactor Fuel and Materials Laboratory, Nuclear Power Institute of China, Chengdu, 610041, China

摘要: 聚变堆面向等离子体材料问题是聚变能商业化应用亟待解决的关键工程问题之一。为应对纯钨材料作为等离子体材料在力学、热学及抗辐照损伤等方面的性能不足,通过添加其它组元形成的钨合金及复合材料成为了近年来聚变堆材料领域尤为关注的研究热点。本文对目前钨基面向等离子体材料的研究进展进行了综述,简要评述其堆服役性能及强化机理,并在此基础上展望该材料未来的研究发展趋势。
- 聚变堆 /
- 面向等离子体材料 /
- 钨基材料
Abstract: Plasma facing materials（PFM） has been one of the most important technological questions for fusion reactor study.Among of traditional PFM candidates（C,Be,and W）,W materials exhibits the most promising applications.However,pure W still has several drawbacks such as low re-crystallization tempera-ture,and high ductile-brittle transition temperature.Therefore,great efforts have been devoted to new W-based alloy and composite materials in recent years.In this paper,the classification and the research pro-gress of the W-based materials are reviewed.Especially,the underlying microscopic mechanisms of enhanced performance of these materials are summarized.At last,the research prospect for W-based PFM is proposed.
- Fusion reactor /
- Plasma facing materials /
- Tungsten-based materials