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Journal Articles

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*

Fusion Science and Technology, 47(1), p.1 - 15, 2005/01

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.

Journal Articles

Development of EC H&CD launcher components for fusion device

Takahashi, Koji; Ishitsuka, Etsuo; Moeller, C. P.*; Hayashida, Kazunori*; Kasugai, Atsushi; Sakamoto, Keishi; Hayashi, Kenichi*; Imai, Tsuyoshi

Fusion Engineering and Design, 66-68, p.473 - 479, 2003/09

 Times Cited Count:11 Percentile:37.8(Nuclear Science & Technology)

For the purpose to confirm the reliability of the front steering concept, tests of the front steering launcher mock-up and neutron irradiation tests of bearings for a movable mirror were carried out under the ITER conditions. The max. stress of the flexible pipes for the movable mirror was measuerd to be 60MPa, much less than the allowable stress and agree with the calculation. No degradation on the performance of bearings was obtained for the assumed fluence of ITER. The mock-up of remote steering(RS) launcher was tested and RF radiation of 0.5MW-3sec and 0.2MW-10sec over 0-10$$^{circ}$$ were performed. No degradation was obseved, either. The new launcher which has the capability of wider range rf beam steering and the corrugated square waveguide with four miter bends that yield the dog-legged structure has been designed, based on the test results. It has been fabricating for high power experiments.

Journal Articles

Development of EC launcher and diamond window for ITER

Takahashi, Koji; Sakamoto, Keishi; Imai, Tsuyoshi; Kasugai, Atsushi; Heidinger, R.*; Thumm, M.*; Moeller, C. P.*

Proceedings of IAEA TM on ECRH Physics and Technology for ITER (CD-ROM), 7 Pages, 2003/00

A front steering (FS) launcher and a remote steering (RS) one have been studied for ITER. In the analysis of a mirror(Cu alloy) for FS launcher, max. temperature of 333$$^{circ}$$C and max. induced stress of 136MPa, less than allowable stress(200MPa), were obtained at the mirror surface under 1MW/1line in CW operation. The efficient transmission ($$eta$$$$>$$95%) at -12$$^{circ}$$$$<$$$$theta$$$$<$$12$$^{circ}$$ and 170GHz was performed for both polarizations in the experiments of a square corrugated waveguide for the RS launcher. RF and pressure tests of the diamond window irradiated by neutron were carried under JA/EU(FZK) collaboration. Neutron fluence of the window was 10$$^{21}$$n/m$$^{2}$$, whereas the estimated annual fluence at the window position is 10$$^{18}$$$$sim$$10$$^{19}$$n/m$$^{2}$$. Transmission of 0.48MW-30sec and 0.2MW-132sec were performed. It was successfully demonstrated that the irradiated window withstood 0.4MPa, which was twice higher than the ITER requirement. Diamond windows are applicable for ITER.

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