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Journal Articles

Beam commissioning of the linac for iBNCT

Naito, Fujio*; Anami, Shozo*; Ikegami, Kiyoshi*; Uota, Masahiko*; Ouchi, Toshikatsu*; Onishi, Takahiro*; Oba, Toshiyuki*; Obina, Takashi*; Kawamura, Masato*; Kumada, Hiroaki*; et al.

Proceedings of 13th Annual Meeting of Particle Accelerator Society of Japan (Internet), p.1244 - 1246, 2016/11

The proton linac installed in the Ibaraki Neutron Medical Research Center is used for production of the intense neutron flux for the Boron Neutron Capture Therapy (BNCT). The linac consists of the 3-MeV RFQ and the 8-MeV DTL. Design average beam current is 10mA. Target is made of Beryllium. First neutron production from the Beryllium target was observed at the end of 2015 with the low intensity beam as a demonstration. After the observation of neutron production, a lot of improvement s was carried out in order to increase the proton beam intensity for the real beam commissioning. The beam commissioning has been started on May 2016. The status of the commissioning is summarized in this report.

Journal Articles

Cryogenic structures of superconducting coils for fusion experimental reactor "ITER"

Nakajima, Hideo; Shimamoto, Susumu*; Iguchi, Masahide; Hamada, Kazuya; Okuno, Kiyoshi; Takahashi, Yoshikazu

Teion Kogaku, 48(10), p.508 - 516, 2013/10

JAEA is procuring both structural materials and structural design of Toroidal Field (TF) coil and Central Solenoid (CS) for ITER. Although 316LN is used in the most parts of the superconducting magnets system, the cryogenic stainless steels, JJ1 and JK2LB, which were newly developed by JAEA and Japanese steel companies, are used in the highest stress area of TF coil case and whole CS conductor jackets, respectively. These two materials became commercially available based on demonstration of productivity and weldability of materials, and evaluations of 4 K mechanical properties of trial products including welded parts. In order to simplify quality control in mass production, JAEA has used materials specified in the material section of "Codes for Fusion Facilities - Rules on Superconducting Magnet Structure (2008)" issued by the Japan Society of Mechanical Engineers (JSME). The design of structural materials, production technology and quality control are described in this paper.

Journal Articles

Evolution of cryogenic structural material development for superconducting coils in fusion reactor

Shimamoto, Susumu*; Nakajima, Hideo; Takahashi, Yoshikazu

Teion Kogaku, 48(2), p.60 - 67, 2013/03

JAEA started development of cryogenic structural material for Tokomak fusion reactor 30 years ago. Because, there was no specialized steel and mechanical data at 4K, JAEA settled target of mechanical characteristics which should satisfy requirements for coil structure at 4K and equipped evaluation facilities at 4K such as tensile test, fatigue test and so on. On the other hand JAEA initiated collaboration with steel industries in order to realize new cryogenic structural material and carried out mechanical evaluation at 4K on numerous samples which were supplied from industries. JAEA contributed standardization of these testing methods at 4K specified in the Japanese industrial standards (JIS). JAEA also supported to establish a construction code for structure of superconducting coil for fusion facility at the Japan Society of Mechanical Engineer (JSME), which is used in manufacture of the ITER toroidal field coil. This paper describes history over 30 years on the material development.

Journal Articles

"ITER" International Thermonuclear Experimental Reactor; From the engineering design activity to the construction phase

Shimamoto, Susumu*; Takahashi, Yoshikazu; Okuno, Kiyoshi

Teion Kogaku, 41(12), p.542 - 552, 2006/12

The purpose of this paper is to explain, from the aspect of superconducting coil system, the concept of ITER (International Thermonuclear Experimental Reactor) to be constructed in France by means of international collaboration of the seven parties. The specifications and results of R&D on superconducting model coils, which were performed during the Engineering Design Activity, were compared with the final design of ITER. The identification of the relevance of model coils to full scale ITER coils and their limitations as well are discussed from the technical and project manage point of view.

Journal Articles

Pulsed field losses and coupling current loop in a large current superconductor

Shimamoto, Susumu*; Murase, Satoru*; Nishii, Kenji*; Naito, Fuminobu*; Matsui, Kunihiro; Takahashi, Yoshikazu; Tsuji, Hiroshi

Denki Gakkai Rombunshi, B, 122(1), p.58 - 63, 2002/01

no abstracts in English

Journal Articles

Analysis of current after normal transition in a cable-in-conduit conductor

Koizumi, Norikiyo; Ando, Toshinari; Takahashi, Yoshikazu; Tsuji, Hiroshi; Shimamoto, Susumu*

IEEE Transactions on Applied Superconductivity, 11(1), p.2575 - 2578, 2001/03

 Times Cited Count:2 Percentile:75.88(Engineering, Electrical & Electronic)

no abstracts in English

Journal Articles

AC loss measurement of 46kA-13T Nb$$_{3}$$Sn conductor for ITER

Takahashi, Yoshikazu; Matsui, Kunihiro; Nishii, Kenji; Koizumi, Norikiyo; Nunoya, Yoshihiko; Isono, Takaaki; Ando, Toshinari; Tsuji, Hiroshi; Murase, Satoru*; Shimamoto, Susumu*

IEEE Transactions on Applied Superconductivity, 11(1), p.1546 - 1549, 2001/03

 Times Cited Count:28 Percentile:21.52(Engineering, Electrical & Electronic)

no abstracts in English

Journal Articles

Development of a 13T-640MJ superconducting pulsed coil for fusion machines

Ando, Toshinari; Hiyama, Tadao; Takahashi, Yoshikazu; Nakajima, Hideo; Kato, Takashi; Isono, Takaaki; Sugimoto, Makoto; Kawano, Katsumi; Koizumi, Norikiyo; Nunoya, Yoshihiko; et al.

Denki Gakkai Rombunshi, B, 120(3), p.449 - 456, 2000/03

no abstracts in English

Journal Articles

Induced circulatin current in a conductor consisting of strands coated with high resistive layer

Koizumi, Norikiyo; Takahashi, Yoshikazu; Kato, Takashi; Tsuji, Hiroshi; Shimamoto, Susumu*

Teion Kogaku, 35(3), p.132 - 142, 2000/03

no abstracts in English

Journal Articles

Development of high performance Nb$$_{3}$$Sn superconducting wire and large current conductor

Isono, Takaaki; Nunoya, Yoshihiko; Matsui, Kunihiro; Sugimoto, Makoto; Yoshida, Kiyoshi; Nishi, Masataka; Takahashi, Yoshikazu; Ando, Toshinari; Tsuji, Hiroshi; Shimamoto, Susumu*

Denki Gakkai Rombunshi, B, 119(11), p.1263 - 1269, 1999/00

no abstracts in English

Journal Articles

Analysis of current distribution in multi-strand cable using distributed model circuit

Koizumi, Norikiyo; Takahashi, Yoshikazu; Tsuji, Hiroshi; Shimamoto, Susumu*

Teion Kogaku, 34(8), p.395 - 403, 1999/00

no abstracts in English

Journal Articles

Development of a 13T-46kA Nb$$_{3}$$Sn conductor and central solenoid model coils for ITER

Takahashi, Yoshikazu; Ando, Toshinari; Hiyama, Tadao; Nakajima, Hideo; Kato, Takashi; Sugimoto, Makoto; Isono, Takaaki; Oshikiri, Masayuki*; Kawano, Katsumi; Koizumi, Norikiyo; et al.

Fusion Engineering and Design, 41(1-4), p.271 - 275, 1998/09

 Times Cited Count:4 Percentile:59.26(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Mechanical properties of 110mm thick hot rolled plates of JJ1 and JK2 for ITER TF coil

*; Nakajima, Hideo; Kawasaki, T.*; *; Tsuji, Hiroshi; F.Wong*; Shimamoto, Susumu*

Proc. of 15th Int. Conf. on Magnet Technology (MT-15), p.989 - 992, 1997/10

no abstracts in English

Journal Articles

Development of winding technique for ITER CS model coil

Hamada, Kazuya; Nakajima, Hideo; Kato, Takashi; Ando, Toshinari; *; Tsuji, Hiroshi; Shimamoto, Susumu*; *; *; Inagaki, J.*

Proc. of 15th Int. Conf. on Magnet Technology (MT-15), p.405 - 408, 1997/10

no abstracts in English

Journal Articles

Development of the CS insert coil

Sugimoto, Makoto; *; Isono, Takaaki; Koizumi, Norikiyo; Nakajima, Hideo; Kato, Takashi; Nunoya, Yoshihiko; Matsui, Kunihiro; Takahashi, Yoshikazu; Ando, Toshinari; et al.

Proc. of 15th Int. Conf. on Magnet Technology (MT-15), p.409 - 412, 1997/00

no abstracts in English

Journal Articles

Performance study of the cryogenic system for ITER CS model coil

Kato, Takashi; Hamada, Kazuya; Kawano, Katsumi; Matsui, Kunihiro; Hiyama, Tadao; Nishida, Kazuhiko*; Honda, Tadaaki*; Taneda, Masanobu*; Sekiguchi, Shuichi*; Otsu, Kiichi*; et al.

ICEC16/ICMC Proceedings, p.127 - 130, 1996/00

no abstracts in English

Oral presentation

Nuclear fusion and superconducting technology

Shimamoto, Susumu*

no journal, , 

no abstracts in English

Oral presentation

Technology of superconducting coils for International Thermonuclear Experimental Reactor

Okuno, Kiyoshi; Takahashi, Yoshikazu; Nakajima, Hideo; Hemmi, Tsutomu; Matsui, Kunihiro; Shimamoto, Susumu*

no journal, , 

The construction of the ITER (International Thermonuclear Experimental Reactor) has started in France under the international collaboration of the seven parties. Magnetic field for ignition, confinement and control of plasma is generated by superconducting coils. The coil system is one of the most important components for the ITER. Japan is manufacturing the major part of the coils. The technology of superconducting coils and the construction schedule are described in this paper.

18 (Records 1-18 displayed on this page)
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