螺线管
电磁线圈
导线
热核聚变
环形场
核工程
超导磁体
导电体
机械工程
聚变能
制作
材料科学
环面
工程类
电气工程
物理
核物理学
等离子体
复合材料
医学
替代医学
病理
作者
M. Huguet,R.J. Thome,Kazumasa Okuno,N. Mitchell
出处
期刊:Fusion Technology
[American Nuclear Society]
日期:1996-12-01
卷期号:30 (3P2B): 1241-1247
被引量:2
标识
DOI:10.13182/fst96-a11963118
摘要
In the six-year Engineering Design Activity (EDA) for the International Thermonuclear Experimental Reactor (ITER)1, some of the major R&D tasks are in the model coil program. One Central Solenoid (CS) and one Toroidal Field (TF) model coil are being designed and manufactured under the collaboration of the European Union, Japan, the Russian Federation and the USA. Both coils will demonstrate the manufacturing technology required for the full-scale coil systems and the CS model coil will be the largest 13 T superconducting system ever built (640 MJ). Forced-flow cooled superconductors are being manufactured in a shared effort by the four ITER Parties for the various stages of fabrication, that is, Nb3Sn superconducting strand production, cabling, jacket material manufacture, and jacketing of conductors. The coils will be tested in two separate facilities with participation by all Parties. Component R&D is also underway in areas such as conductor and joint performance, jacket and insulation material properties, and manufacturing processes for large steel structure fabrication. This paper summarizes the status of the program.
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