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Progress towards a Better Be/Cu Joining for ITER First Wall in China
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作者 CHEN Jiming WANG X. S. +10 位作者 WANG Z.H. WAN Z. J. LIU Xiang zhang P. C. zhang Fu TANG Y. M. LI Z. N. XU Zengyu WANG L. zhang nianman PAN Chuanhong 《Southwestern Institute of Physics Annual Report》 2006年第1期178-179,共2页
ITER will be constructed and has its first plasma at 2016. It will demonstrate the integration of technologies for reactors and serve as a test facility for advanced components such as blankets. China has joined the p... ITER will be constructed and has its first plasma at 2016. It will demonstrate the integration of technologies for reactors and serve as a test facility for advanced components such as blankets. China has joined the program and will have her contribution to its construction, operation and so on. One of the in-vessel components fabricated by China is the shield blanket, which consists of first wall (FW) and shield blocks. FW is a joint of Be/Cu/SS, with Be as plasma facing material. 展开更多
关键词 中国 等离子体
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