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Report No.
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Design performance of front steering-type electron cyclotron launcher for ITER

Takahashi, Koji; Imai, Tsuyoshi; Kobayashi, Noriyuki*; Sakamoto, Keishi; Kasugai, Atsushi; Hayakawa, Atsuro*; Mori, Seiji*; Mori, Kensuke*

An applicability of a front steering type EC launcher to a fusion reactor is described with the design and thermal, electromagnetic and nuclear analysis using the ITER design conditions. Maximum stress of the support keys of the front shield module, the welds of the keys and the mirror shaft induced by electromagnetic force are 85.5MPa and 34.1MPa and 22MPa, respectively, which are less than 1.5Sm of stainless steel(205MPa). Maximum thermal stress in the front shield module and the mirror, which are 249MPa and 350MPa, respectively, are obtained at the inner surface of a stainless steel cooling tube. The stresses are less 3Sm of stainless steel at 200$$^{circ}$$C(410MPa). The annual neutron fluence and the dose rate at the vacuum window(closure plate) are estimated to be 10$$^{13}$$$$sim$$10$$^{12}$$ n/cm$$^{2}$$/yr and 45$$mu$$Sv/h, respectively that satisfy the shield criteria of the ITER. It appears that the design of the front steering type EC launcher is applicable to an ITER grade reactor.

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