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Journal Articles

Estimation of the lifetime of resin insulators against baking temperature for JT-60SA in-vessel coils

Sukegawa, Atsuhiko; Murakami, Haruyuki; Matsunaga, Go; Sakurai, Shinji; Takechi, Manabu; Yoshida, Kiyoshi; Ikeda, Yoshitaka

Fusion Engineering and Design, 98-99, p.2076 - 2079, 2015/10

 Times Cited Count:1 Percentile:17.75(Nuclear Science & Technology)

The JT-60SA project is a EU - JA satellite tokamak under Broader Approach in support of the ITER project. In-vessel coils are designed and assembled by JA. The resin-insulator is required to have a heat resistance against the baking temperature of vacuum vessel of $$sim$$200$$^{circ}$$C (40000 hour). Thus the assessment of the heat load is fundamental for the design of the coils. However, the estimation of the lifetime of resin-insulator under the high-temperature region has not been examined. In the present study, the estimation of the lifetime of seven candidate resin-insulators such as epoxy resin and cyanate-ester resin under the $$sim$$220$$^{circ}$$C temperature region have been performed for the current coils design. Weight reduction of the seven candidate insulators was measured at different heating times under 180$$^{circ}$$C, 200$$^{circ}$$C and 220$$^{circ}$$C environment using three thermostatic ovens, respectively. The reduction of the insulators has been used as input for Weibull-analysis towards Arrhenius-plot. Lifetime of the resins has been estimated for the first time at the high temperature region by the plot. Lifetime of the resin-insulators have been evaluated and discussed as well as the available temperature of the in-vessel coils.

Journal Articles

Neutronic analysis of fusion tokamak devices by PHITS

Sukegawa, Atsuhiko; Takiyoshi, Koji*; Amano, Toshio*; Kawasaki, Hiromitsu*; Okuno, Koichi*

Progress in Nuclear Science and Technology (Internet), 1, p.36 - 39, 2011/02

A complete 3D radiation shielding analysis by PHITS has been performed for the JT-60U and JT-60 superconducting tokamak device (JT-60SA) in the present study. The PHITS has been developed for high energy particles physics in Japan. The neutron and photon transport analysis less than 20 MeV with the general cross section library is the same algorism of MCNP-4C code. The monoenergetic neutron (E$$_{rm n}$$ = 2.45 MeV) of the DD fusion devices are used for the neutron source in the analysis. The neutron source distribution are available a toroidally symmetric source for the analysis. The toroidal source has a poloidal distribution, so that a source routine in the PHITS has been replaced a newly developed source routine. The visual nuclear responses such as the neutron flux distribution, the photon flux distribution, the nuclear heating of the coils and the dose rate around the devices has been calculated by the PHITS for the fusion tokamak devices. Initial results by the PHITS have been demonstrated.

Journal Articles

Status of JT-60SA tokamak under the EU-JA broader approach agreement

Matsukawa, Makoto; Kikuchi, Mitsuru; Fujii, Tsuneyuki; Fujita, Takaaki; Hayashi, Takao; Higashijima, Satoru; Hosogane, Nobuyuki; Ikeda, Yoshitaka; Ide, Shunsuke; Ishida, Shinichi; et al.

Fusion Engineering and Design, 83(7-9), p.795 - 803, 2008/12

 Times Cited Count:17 Percentile:72.99(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Applying the remote maintenance technology to the large scale hot laboratory

Sakamoto, Naoki; Yoshikawa, Katsunori; Kushida, Naoya; Nakamura, Yasuo; Sukegawa, Kiyoshi*

Nihon Hozen Gakkai Dai-5-Kai Gakujutsu Koenkai Yoshishu, p.226 - 230, 2008/07

no abstracts in English

Oral presentation

Present design of radiation shielding on JT-60 Super Advanced

Sukegawa, Atsuhiko; Sakurai, Shinji; Masaki, Kei; Kizu, Kaname; Tsuchiya, Katsuhiko; Shibama, Yusuke; Hayashi, Takao; Tamai, Hiroshi; Yoshida, Kiyoshi; Matsukawa, Makoto; et al.

no journal, , 

no abstracts in English

Oral presentation

Current estimation methods of superconducting coil on JT-60 super advanced

Sukegawa, Atsuhiko; Kizu, Kaname; Masaki, Kei; Tsuchiya, Katsuhiko; Sakurai, Shinji; Yoshida, Kiyoshi; Matsukawa, Makoto; Fujita, Takaaki; Konno, Chikara

no journal, , 

no abstracts in English

Oral presentation

Development of safety review method for hot laboratories, 3; Remote maintenance techniques for hot laboratories

Sakamoto, Naoki; Yoshikawa, Katsunori; Kushida, Naoya; Nagamine, Tsuyoshi; Sukegawa, Kiyoshi*

no journal, , 

no abstracts in English

Oral presentation

Irradiation test for insulation of JT-60SA in-vessel coils

Murakami, Haruyuki; Sukegawa, Atsuhiko; Yoshida, Kiyoshi

no journal, , 

no abstracts in English

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