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Appliocation of High Z materials as Plasma Facing Materials

高Z材料作为等离子体表面材料的应用

基本信息

批准号：
10308020
负责人：
TANABE Tetsuo
金额：
$ 20.48万
依托单位：
Nagoya University
依托单位国家：
日本
项目类别：
Grant-in-Aid for Scientific Research (A).
财政年份：
1998
资助国家：
日本
起止时间：
1998 至 2000
项目状态：
已结题

来源：
https://kaken.nii.ac.jp/grant/KAKENHI-PROJECT-10308020/
关键词：
Divetor High Z metals Molybdenum Tungsten Plasma-Wall Interactions High heat flux hydrogen ion Hydrogen recycling プラズマ壁相互作用高熱滋束高熱流束

项目摘要

Properties of high Z materials as plasma facing materials, such as hydrogen recycling, thermal response to plasma heat load, high Z impurity release and behavior of their ions in plasmas, have been examined by various technique. Main conclusions are summarized as follows,(1) The W bulk limiter operated with preheating above 800K withstood plasma heat load of about〜20MW/m^2 for a few seconds except slight surface melting during the highest heat load shot. However it was severely damaged when operated at around 500K(2) The C/W twin limiter experiments gave very useful information on how low- and high-Z materials behave for the case of simultaneous utilization as plasma facing maerials (PFM) such like cross contamination process, influences of large mass difference in the hydrogen reflection and deposition, and so on.(3) About 60% of the total convection heat was absorbed in the vacuum plasma splayed-W (VPS-W) coated poloidal limiters, and the ohmic plasma with the density as high as 5×10^<13> cm^<-3> was sustained. Most of the VPS-W coated limiters tolerated to the heat load of〜20MW/m^2. However some limiters were heavily damaged. Probably their curved shape gave strong thermal stress, resulting in the exfoliation of the W layer. Operation at below DBTT would enhance the crack propagation.These series of W limiters experiments in TEXTOR have probed that W is applicable as PFM and divertor plate, if its central accumulation are avoided by NBI and/or ICRH heating. Nevertheless, some concerns are still remaining, those are, difficulty of plasma start-up, W behavior in higher temperature plasma, and materials selection.

利用各种技术研究了高Z材料作为等离子体表面材料的氢再循环、等离子体热负荷的热响应、高Z杂质释放及其离子在等离子体中的行为等性能。主要结论如下：(1)在800K以上预热条件下，W本体限位器除在最高热负荷喷射时表面有轻微熔化外，在几秒钟内可承受约20MW/m^2的等离子体热负荷。(2) C/W双限制器实验为同时用作等离子体表面材料（PFM）的低z和高z材料的行为提供了非常有用的信息，如交叉污染过程、大质量差对氢反射和沉积的影响等。(3)真空等离子体溅射w （VPS-W）涂层极向限流器吸收了约60%的对流总热量，维持了密度高达5×10^<13> cm^<-3>的欧姆等离子体。大多数VPS-W涂层限制器可承受~ 20MW/m^2的热负荷。然而，一些限制器严重受损。可能它们弯曲的形状产生了很强的热应力，导致W层脱落。在低于DBTT的条件下操作，会增强裂纹扩展。在TEXTOR中进行的这一系列W限制器实验表明，如果通过NBI和/或ICRH加热避免了W的中心积聚，则W适用于PFM和导流板。然而，仍然存在一些问题，即等离子体启动困难，高温等离子体中的W行为以及材料选择。