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Journal Articles

Analysis of maximum voltage transient of JT-60SA toroidal field coils in case of fast discharge

Novello, L.*; Cara, P.*; Coletti, A.*; Gaio, E.*; Maistrello, A.*; Matsukawa, Makoto; Philipps, G.*; Tomarchio, V.*; Yamauchi, Kunihito

IEEE Transactions on Applied Superconductivity, 26(2), p.4700507_1 - 4700507_7, 2016/03

 Times Cited Count:6 Percentile:39.96(Engineering, Electrical & Electronic)

Journal Articles

Manufacturing study and trial fabrication of radial plate for ITER toroidal field coil

Abe, Kanako*; Nakajima, Hideo; Hamada, Kazuya; Okuno, Kiyoshi; Kakui, Hideo*; Yamaoka, Hiroto*; Maruyama, Naoyuki*

IEEE Transactions on Applied Superconductivity, 16(2), p.807 - 810, 2006/06

 Times Cited Count:11 Percentile:52.53(Engineering, Electrical & Electronic)

no abstracts in English

Journal Articles

Design study of superconducting coils for the fusion DEMO plant at JAERI

Isono, Takaaki; Koizumi, Norikiyo; Okuno, Kiyoshi; Kurihara, Ryoichi; Nishio, Satoshi; Tobita, Kenji

Fusion Engineering and Design, 81(8-14), p.1257 - 1261, 2006/02

 Times Cited Count:5 Percentile:37.87(Nuclear Science & Technology)

In order to realize an economically competitive power generation system, generation of a higher field is required. Toroidal Field (TF) coils of fusion DEMO plant at JAERI are required to generate magnetic field of 16 to 20 T. To realize this high field, advanced superconducting materials, such as Nb$$_3$$Al and high temperature superconductor (HTS), are considered. HTS has enough performance in a 20-T field at 4 K, and a forced-cooled type HTS conductor using a silver alloy sheathed Bi-2212 round wire has been proposed. Required areas of superconductor, structure, stabilizer, coolant and insulator in the cross section of coil winding have been calculated. However, there are many technical issues to be solved, such as accurate temperature control during heat treatment in an atmosphere of oxygen. On the other hand, a large coil using Nb$$_3$$Al has been developed by JAERI, and major technology to fabricate a 16-T Nb$$_3$$Al coil was developed. Validity and issues of grading the winding area are discussed, and there is a possibility to increase a field up to around 17 T using the method.

Journal Articles

An Approach for development of technical structural standard in ITER

Nakahira, Masataka; Takeda, Nobukazu

Hozengaku, 4(4), p.47 - 52, 2006/01

The technical structural standard for ITER (International Thermonuclear Experimental Fusion Reactor) should be innovative because of their quite different features of safety and mechanical components from nuclear fission reactors, and the necessity of introducing several new fabrication and examination technologies. Recognizing the international importance of Fusion Standard, Japan and ASME has started the cooperation development of the Fusion Standard. This paper shows the special features of ITER from view points of safety, design and fabrication, and proposes approach for development of the fusion standard.

Journal Articles

Development of a heat-resistant neutron shielding resin for the national centralized tokamak

Morioka, Atsuhiko; Sakurai, Shinji; Okuno, Koichi*; Tamai, Hiroshi

Purazuma, Kaku Yugo Gakkai-Shi, 81(9), p.645 - 646, 2005/09

A 300 $$^{circ}$$C heat-resistant neutron shielding material is newly developed, which consists of phenol-based resin with 5 weight-% boron. The neutron shielding performance of the developed resin, examined by the $$^{252}$$Cf neutron source, is almost the same as that of the polyethylene. The resin is applicable to the port section of vacuum vessel of the DD plasma device to suppress the streaming neutrons and to reduce the nuclear heating of the superconducting coils.

Journal Articles

Proposals for the final design of the ITER central solenoid

Yoshida, Kiyoshi; Takahashi, Yoshikazu; Mitchell, N.*; Bessette, D.*; Kubo, Hiroatsu*; Sugimoto, Makoto; Nunoya, Yoshihiko; Okuno, Kiyoshi

IEEE Transactions on Applied Superconductivity, 14(2), p.1405 - 1409, 2004/06

 Times Cited Count:16 Percentile:60.91(Engineering, Electrical & Electronic)

The ITER Central Solenoid (CS) is 12m high and 4m in diameter. The CS consists of a stack of 6electrically independent modules to allow control of plasma shape. The modules are compressed vertically by a pre-compression structure to maintain contact between modules. The CS conductor is CIC conductor with Nb$$_{3}$$Sn strands and a steel conduit. The CS model coil and insert coil test results have shown that the conductor design must be modified to achieve an operation margin. This required either to increase the cable diameter or to use strand with a higher current capability. A bronze-process (NbTi)$$_{3}$$Sn strand is proposed to achieve a higher critical magnetic field. A square conduit with a high Mn stainless steel is proposed as it can satisfy fatigue requirements. The inlets are in the high stress region and any stress intensification there must be minimized. The pre-compression structure is composed of 9tie plates to reduce the stress on the cooling pipes. These design proposals satisfy all ITER operational requirements.

Journal Articles

Objectives and design of the JT-60 superconducting tokamak

Ishida, Shinichi; Abe, Katsunori*; Ando, Akira*; Cho, T.*; Fujii, Tsuneyuki; Fujita, Takaaki; Goto, Seiichi*; Hanada, Kazuaki*; Hatayama, Akiyoshi*; Hino, Tomoaki*; et al.

Nuclear Fusion, 43(7), p.606 - 613, 2003/07

 Times Cited Count:33 Percentile:70.69(Physics, Fluids & Plasmas)

no abstracts in English

Journal Articles

Electromagnetic phenomenon in superconducting magnet for fusion facility; Forced flow superconducting magnet

Hamada, Kazuya; Koizumi, Norikiyo

Purazuma, Kaku Yugo Gakkai-Shi, 78(7), p.616 - 624, 2002/07

In the Tokamak type fusion reactor design, a forced flow superconducting coil is applied from the viewpoint to high magnetic field, high withstand voltage performance and large electromagnetic force. In the forced flow magnets, it is well known that various electromagnetic phenomena are occurred by zero resistance and diamagnetic effect of superconductor and complicated structure of cable in conduit conductor (CICC). In the R&D of CICC, the study of hysteresis losses and coupling losses CICC have a lot of progress. For example, using the optimization of filament arrangement in superconducting strand and control of contact resistance of strand, ITER model coil project have a large achievement.

Journal Articles

ITER project and its superconducting coils

Yoshida, Kiyoshi

Teion Kogaku, 37(5), p.190 - 201, 2002/05

The design and development of the International Thermonuclear Experiment Reactor (ITER) has been performed since 1992 based on the international agreement of the Engineering Design Activities (EDA). The design of the main machine and the development of key components were successfully completed by July 2001. The technical specifications of ITER machine are being prepared for the order of its fabrications on the Co-ordinate Technical Activities (CTA). The construction of ITER is expected to start by 2005. The ITER machine uses the superconducting coils to confine and shaped the plasma. The superconducting coil system must be reliability operated to perform the plasma experiment. The superconducting coil system needs 28 % of the direct capital costs and long manufacturing period (6 years and 6 months). A strand for the superconducting conductor is the first procurement component in the ITER. This paper explains the present design and status of the ITER project and its superconducting coils.

Journal Articles

Journal Articles

Analytical studies on hotspot temperature of cable-in-conduit conductors

Yoshida, Kiyoshi; Takigami, Hiroyuki*; Kubo, Hiroatsu*

Teion Kogaku, 36(11), p.617 - 625, 2001/11

no abstracts in English

Journal Articles

First test results for the ITER central solenoid model coil

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

Fusion Engineering and Design, 56-57, p.59 - 70, 2001/10

 Times Cited Count:17 Percentile:75.92(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Analytical studies on the hotspot temperature of cable-in-conduit conductors

Yoshida, Kiyoshi; Takigami, Hiroyuki*; Kubo, Hiroatsu*

Cryogenics, 41(8), p.583 - 594, 2001/08

 Times Cited Count:8 Percentile:38.42(Thermodynamics)

no abstracts in English

Journal Articles

CS model coil test facility

Kato, Takashi; Nakajima, Hideo; Isono, Takaaki; Hamada, Kazuya; Kawano, Katsumi; Sugimoto, Makoto; Nunoya, Yoshihiko; Koizumi, Norikiyo; Matsui, Kunihiro; Oshikiri, Masayuki*; et al.

Teion Kogaku, 36(6), p.315 - 323, 2001/06

no abstracts in English

Journal Articles

Acoustic emission in ITER CS model coil and CS insert coil

Ninomiya, Akira*; Arai, Kazuaki*; Takano, Katsutoshi*; Nakajima, Hideo; Michael, P.*; Martovetsky, N.*; Takahashi, Yoshikazu; Kato, Takashi; Ishigooka, Takeshi*; Kaiho, Katsuyuki*; et al.

Teion Kogaku, 36(6), p.344 - 353, 2001/06

no abstracts in English

Journal Articles

Experiment of the central solenoid model coil for the ITER

Tsuji, Hiroshi; Team for the ITER CS Model Coil Experiment

Heisei-12-Nendo Denki Gakkai Genshiryoku Kenkyu Shiryo (NE-00-2), p.7 - 12, 2000/09

no abstracts in English

Journal Articles

Supercritical helium pump

Kato, Takashi

Tabo Kikai, 28(9), p.536 - 545, 2000/09

no abstracts in English

Journal Articles

AC loss performance of the 100kwh SMES model coil

Hamajima, Takataro*; Hanai, Satoshi*; Wachi, Yoshihiro*; Shimada, Mamoru*; Ono, Michitaka*; Martovetsky, N.*; Zbasnik, J.*; Moller, J.*; Takahashi, Yoshikazu; Matsui, Kunihiro; et al.

IEEE Transactions on Applied Superconductivity, 10(1), p.812 - 815, 2000/03

 Times Cited Count:10 Percentile:54.12(Engineering, Electrical & Electronic)

no abstracts in English

JAEA Reports

ITER cryostat main chamber and vacuum vessel pressure suppression system design

*; Nakahira, Masataka; Takahashi, Hiroyuki*; Tada, Eisuke; *; *

JAERI-Tech 99-026, 158 Pages, 1999/03

JAERI-Tech-99-026.pdf:6.58MB

no abstracts in English

Journal Articles

Development and performance test results of 50kA vapor-cooled current lead for ITER

Sugimoto, Makoto; Isono, Takaaki; Hamada, Kazuya; Kawano, Katsumi; Koizumi, Norikiyo; Nunoya, Yoshihiko; Matsui, Kunihiro; Kato, Takashi; Nakajima, Hideo; Takahashi, Yoshikazu; et al.

Teion Kogaku, 33(8), p.549 - 560, 1998/00

no abstracts in English

75 (Records 1-20 displayed on this page)