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9篇 您的检索式:作者名="N.Yoshida"
    题名 作者 年代 出处 被引量
1查看详情显示文摘R.Ota J.Fukunaga N.Yoshida 0,,:1
2钨和碳基材料在高能脉冲电子束轰击下的腐蚀和腐蚀产物N.Yoshida N.Noda 刘翔 张斧 许增裕 刘永 2002中国核科技报告2002,,1:0
3聚变堆与聚变堆材料/钨和碳基材料在高能脉冲电子束轰击下的腐蚀和腐蚀产物显示文摘刘翔 N.Yoshida N.Noda 张斧 许增裕 刘永 2001核工业西南物理研究院年报2001,,1:0
4The Erosion and Erosion Products of Tungsten and Carbon Based Materials Bombarded by High Energy Pulse Electron Beam显示文摘High Z and low Z materials are both the candidate plasma facing materials (PFM), up to now, the typical representative of high Z materials is tungsten, and the representatives of low Z materials are carbon materials (such as graphite, C/C composite) and beryllium. Most of these materials have been used as PFM limiters and diverter armor tiles of tokamak machines, tungsten, molybdenum and C/C composite are always used as high heat flux components.LIUXiang N.Yoshida N.Noda ZHANGFu XUZengyu LIUYong 2001Southwestern Institute of Physics Annual Report2001,,1:0
52.14 室温下注入钨中的氦的热解吸显示文摘钨是ITER及未来聚变堆中偏滤器靶板的主要候选材料之一。由于聚变堆中要实现D-T反应,面对等离子体材料除需承受高热负荷外,还要受到氦离子辐射。氦在材料中的滞留与热解吸行为便倍受关注。由于钨的熔点很高,要获得完整的热解吸谱将较为困难。因此至今为止,相关的研究报道较少。本文中。张斧 许增裕 刘翔 谌继明 徐颖 N.Yoshida H.Iwakiri 2002核工业西南物理研究院年报2002,,1:0
6Erosion and Modifications of Tungsten-Coated Carbon and Copper Under High Heat Flux显示文摘Tungsten-coated carbon and copper was prepared by vacuum plasma spraying (VPS)and inert gas plasma spraying (IPS), respectively. W/CFC (Tungsten /Carbon Fiber-Enhancedmaterial) coating has a diffusion barrier that consists of W and Re multi-layers pre-deposited byphysical vapor deposition on carbon fiber-enhanced materials, while W/Cu coating has a gradedtransition interface. Different grain growth processes of tungsten coatings under stable and tran-sient heat loads were observed, their experimental results indicated that the recrystallizing tem-perature of VPS-W coating was about 1400 ℃ and a recrystallized columnar layer of about 30μmthickness was formed by cyclic heat loads of 4 ms pulse duration. Erosion and modifications ofW/CFC and W/Cu coatings under high heat load, such as microstructure changes of interface,surface plastic deformations and cracks, were investigated, and the erosion mechanism erosionproducts) of these two kinds of tungsten coatings under high heat flux was also studied.刘翔 S.Tamura K.Tokunaga N.Yoshida 张斧 许增裕 葛昌纯 N.Noda 2003Plasma Science and Technology2003,5,4:0
7Development of High Quality Tungsten Coating as Plasma Facing Materials and Components显示文摘The control of core plasma and impurity level of edge plasma has been greatly improved with the development of controlled fusion technology. Refractory metal tungsten or its alloy was paid more attentions owing to its high melting temperature, goodLIUXiang XUZengyu LIUYong GEChangchun S.Tamura N.Yoshida 2002Southwestern Institute of Physics Annual Report2002,,1:0
8Microstructure and Texture Changes of Tungsten-Rhenium coated on Carbon Fiber Composite during Annealing显示文摘Since tungsten was chose as the divertor tiles of 1TER, the investigation of tungsten and its coating as plasma facing material (PFM) have been paid more attentions by fusion scientists all over the world. Recent years, tungsten coatings have beenLIUXiang XUZengyu S.Tamura N.Yoshida 2002Southwestern Institute of Physics Annual Report2002,,1:0
9Thermal Desorption of Helium Implanted in Tungsten at RT显示文摘Tungsten is envisaged as one of the main candidate materials for divertor plate of ITER and future fusion reactors. Due to D-T reaction, PFMs would suffer helium irradiation from plasma additional to the high heat loads. Helium retention and thermal desorption behavior are largely concerned.ZHANGFu XUZengyu LIUXiang CHENJiming XUYing N.Yoshida H.Iwakiri 2002Southwestern Institute of Physics Annual Report2002,,1:0
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