Japanese developments of fusion reactor plasma facing components
Japanese developments of fusion reactor plasma facing components
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DOI：
10.1016/s0920-3796(00)00349-5
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发表时间：
2000-11
影响因子：
1.7
通讯作者：
T. Hino;M. Akiba
中科院分区：
文献类型：
--
作者：
T. Hino;M. Akiba
对于ITER和聚变反应堆，日本在等离子体表面材料和低活化材料的评估研究以及等离子体表面组件的开发方面取得了重大进展。研究了碳钨混合材料、碳尘、铁素体钢、钒合金和碳化硅等容器内材料的等离子体相互作用。特别是对引起氢脆的气体脱附、燃料氢保留和氢吸收进行了研究，并讨论了作为容器内材料的适用性。对于ITER的等离子体面组件，新材料和新技术得到了发展。开发了高导热系数（500w /m / K）的三维CFC、5mm厚钨涂层CVD技术、无氧铜包弥散强化铜冷却管（OFCu包DS Cu）、无银钎焊碳纤维增强碳复合材料（CFC）与铜合金的连接技术。用无银钎焊将CFC组件钎焊在OFCu包覆的DS Cu上，可承受20 MW/m2的热流密度。针对核聚变反应堆，研制了一种低活化铁素体钢的冷却结构。
For ITER and fusion reactors, evaluation studies on plasma facing materials and low activation materials, and developments of plasma facing components have achieved significant advances in Japan. Plasma material interactions of in-vessel materials such as carbon-tungsten mixed material, carbon dust, ferritic steel, vanadium alloy and SiC have been investigated. In particular, gas desorption, fuel hydrogen retention and hydrogen absorption which causes hydrogen embrittlement have been examined, and the suitability as an in-vessel material has been discussed. For the plasma facing components of ITER, new materials and technologies have been developed. 3-D-CFC with high thermal conductivity (500 W/m per K), CVD technique for tungsten coating with 5-mm thickness, oxygen free copper clad dispersion strengthened copper cooling tube (OFCu clad DS Cu), and joining technique between carbon fiber reinforced carbon composite (CFC) and copper alloy with silver-free braze have been developed. A component of CFC brazed onto OFCu clad DS Cu with silver-free braze withstood a heat flux of 20 MW/m2. For fusion reactors, a cooling structure made of low activation ferritic steel has been developed.