Home / Store / Journals / Electronic Articles / Fusion Science and Technology / Volume 6 / Number 2P1 / Pages 253-264
Hiroyuki Kojima, Hiroshi Miyata, Hiroshi Kimoto, Susumu Hioki, Teruhiro Takizawa, Masayuki Furuyama
Fusion Science and Technology / Volume 6 / Number 2P1 / Pages 253-264
Format:electronic copy (download)
The poloidal field coil (PFC) with a cooling pipe for nuclear fusion equipment is a very large scale coil with complex geometry. Confirmation of its reliability under operating loads must be made during the design process. The stress analysis of the coil conductor is carried out, including the following items:
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