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Oral presentation

Trial fabrication of basic segments of ITER TF coil structures

Chida, Yutaka; Iguchi, Masahide; Nakajima, Hideo

no journal, , 

no abstracts in English

Oral presentation

Qualification test results of the stainless steel for ITER TF coil structures

Iguchi, Masahide; Saito, Toru; Kawano, Katsumi; Tsutsumi, Fumiaki; Takano, Katsutoshi; Nakajima, Hideo; Chida, Yutaka

no journal, , 

no abstracts in English

Oral presentation

The Impact of specimen geometry on tensile mechanical property at 4K

Saito, Toru; Kawano, Katsumi; Hamada, Kazuya; Iguchi, Masahide; Tsutsumi, Fumiaki; Takano, Katsutoshi; Nakajima, Hideo

no journal, , 

no abstracts in English

Oral presentation

Status of conductor manufacturing preparation for ITER Central Solenoid (CS) coil

Hamada, Kazuya; Nunoya, Yoshihiko; Isono, Takaaki; Takahashi, Yoshikazu; Hemmi, Tsutomu; Matsui, Kunihiro; Nabara, Yoshihiro; Kawano, Katsumi; Oshikiri, Masayuki; Tsutsumi, Fumiaki; et al.

no journal, , 

ITER Central Solenoid (CS) coil conductor is composed of 576 Nb$$_{3}$$Sn superconducting strand and 288 Cu strand protected by a circle-in-square shaped sheath tube (conduit) with an outer dimension of 49 mm and inner hoe diameter of 32.6 mm. The conduit materila is high manganese stainless steel (JK2LB) with a low thermal contract charactarisitic and low fatigue crack grwoth rate, developed by JAEA. The Japan Atomic Energy Agency (JAEA) as the Japanese Domestic Agency (JADA) of the ITER project has the responsibility to procure 100% of the ITER CS Coil conductors. Manufactured conductors will be transported to US, formed to CS coil shape and installed in ITER. Prior to conductor procurement, JAEA manufactured 4-m long conductor sample. The sample will be tested in SULTAN facility in Switzerland. In the conferece, results of SULTAN test and charactarisitic of conduit materila are reported. And status of CS condcutor procurement will be introduced.

Oral presentation

Development of manufacture technology of radial plate for ITER TF coil

Takano, Katsutoshi; Koizumi, Norikiyo; Matsui, Kunihiro; Hemmi, Tsutomu; Nakajima, Hideo

no journal, , 

no abstracts in English

Oral presentation

Evaluation technique of Nb$$_3$$Sn superconducting strand for ITER TF coil

Nabara, Yoshihiro; Nunoya, Yoshihiko; Isono, Takaaki; Koizumi, Norikiyo; Hamada, Kazuya; Matsui, Kunihiro; Hemmi, Tsutomu; Yoshikawa, Masatoshi*; Uno, Yasuhiro; Oshikiri, Masayuki; et al.

no journal, , 

no abstracts in English

Oral presentation

Status of fabrication of ITER superconducting magnets in Japan

Koizumi, Norikiyo; Takahashi, Yoshikazu; Nunoya, Yoshihiko; Hamada, Kazuya; Isono, Takaaki; Nabara, Yoshihiro; Matsui, Kunihiro; Hemmi, Tsutomu; Chida, Yutaka; Iguchi, Masahide; et al.

no journal, , 

no abstracts in English

Oral presentation

Analytical model to calculate critical current of a bent Nb$$_{3}$$Sn strand

Koizumi, Norikiyo; Murakami, Haruyuki; Hemmi, Tsutomu; Nakajima, Hideo

no journal, , 

no abstracts in English

Oral presentation

Development of insulation technology for ITER TF coils

Hemmi, Tsutomu; Matsui, Kunihiro; Koizumi, Norikiyo; Takano, Katsutoshi; Nakajima, Hideo

no journal, , 

Insulations for the ITER TF coils are required withstanding against a designed neutron fluence of 10$$^{22}$$ n/m$$^{2}$$. As a candidate for resin, Cyanate Ester (CE) and epoxy blended resin, which has sufficiently high radiation hardness, will be applied for the TF coils instead of epoxy resins. JAEA is performing the some trials for the insulation and impregnation using the CE blended resin to optimize the insulation work. In this report, impregnation trials simulating the simultaneous impregnation of the conductor insulation and the Double Pancake (DP) insulation and fabrication of the bonded Glass and Polyimide tape are reported.

Oral presentation

Development of the winding technology of 1/3 scale winding for ITER TF coil

Matsui, Kunihiro; Koizumi, Norikiyo; Hemmi, Tsutomu; Takano, Katsutoshi; Iguchi, Masahide; Nakajima, Hideo

no journal, , 

no abstracts in English

Oral presentation

The Design of helium distribution system for JT-60SA, 2

Kamiya, Koji; Komeda, Masao*; Kizu, Kaname; Yoshida, Kiyoshi

no journal, , 

JT-60SA helium refrigerator system cools the superconducting coils, high temperature superconducting current leads, the thermal shield, and cryopump. In addition to the heat load from those components, the circulation pump power to cool the superconducting coils with the supercritical helium is added. Therefore, evaluation of the power defined as the mass flow rate times the pressure drop for circulation pump is very important. JT-60SA is equipped with two circulation pumps refered as CP. CP1 cools the toroidal field (TF) coils and structures which EU is in charge of manufacture, and CP2 cools the central solenoids and the equilibrium field (EF) coils which Japan is in charge of manufacture. The required pressure drop of CP1 and CP2 are 120 kPa and 100 kPa, respectively. The current presentation reports optimization of the mass flow rate for CP2, and its resultant pressure drop calculation satisfies the required pressure drops.

Oral presentation

Start-up of manufacture of superconducting magnet system for the JT-60SA

Yoshida, Kiyoshi; Tsuchiya, Katsuhiko; Kizu, Kaname; Murakami, Haruyuki; Kamiya, Koji

no journal, , 

no abstracts in English

Oral presentation

Detailed support design of thermal shield for JT-60SA

Onishi, Yoshihiro; Asakawa, Shuji; Ichige, Toshikatsu; Hoshi, Ryo; Kamiya, Koji; Yoshida, Kiyoshi

no journal, , 

no abstracts in English

Oral presentation

Performance verification test of NbTi joint for JT-60SA EF coil

Murakami, Haruyuki; Kizu, Kaname; Tsuchiya, Katsuhiko; Yoshida, Kiyoshi; Obana, Tetsuhiro*; Takahata, Kazuya*; Hamaguchi, Shinji*; Yanagi, Nagato*; Imagawa, Shinsaku*; Mito, Toshiyuki*; et al.

no journal, , 

no abstracts in English

Oral presentation

Dynamic characteristics of the cryogenic hydrogen system for a spallation neutron source at J-PARC for a 300-kW proton beam operation

Tatsumoto, Hideki; Aso, Tomokazu; Kato, Takashi; Otsu, Kiichi

no journal, , 

no abstracts in English

Oral presentation

Forced flow boiling heat transfer of supercritical hydrogen

Tatsumoto, Hideki; Shiotsu, Masahiro*; Kobayashi, Hiroto*; Yoshikawa, Kotaro*; Shirai, Yasuyuki*; Hata, Koichi*; Kobayashi, Hiroaki*; Naruo, Yoshihiro*; Inatani, Yoshifumi*

no journal, , 

no abstracts in English

16 (Records 1-16 displayed on this page)
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