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Journal Articles

Study of ITER toroidal field coil manufacturing procedure

Nagamoto, Yoshifumi*; Osemochi, Koichi*; Shimada, Mamoru*; Senda, Ikuo*; Koizumi, Norikiyo; Chida, Yutaka; Iguchi, Masahide; Nakajima, Hideo

Teion Kogaku, 47(3), p.200 - 205, 2012/03

Based on the results of the sub- and full-scale trials, the TF coil and TF coil structure manufacturing procedures were considered. Radial plate (RP) will be manufactured by assembling 10 sets of segments with Laser Beam Welding. Cover plates (CPs) will be manufactured by 3 different methods, depending on their geometry. For Winding pack (WP), winding system to enable to measurement of the conductor length with the accuracy of 0.01% for serial production was designed. Assembling procedure and groove types of narrow gap TIG welding for coil structures were determined. Hereafter, technical improvements will be considered in order to aim for further optimization of manufacturing.

Journal Articles

Development of the ITER toroidal field coil winding pack in Japan

Koizumi, Norikiyo; Nakajima, Hideo; Matsui, Kunihiro; Hemmi, Tsutomu; Takano, Katsutoshi; Okuno, Kiyoshi; Hasegawa, Mitsuru*; Kakui, Hideo*; Senda, Ikuo*

IEEE Transactions on Applied Superconductivity, 20(3), p.385 - 388, 2010/06

 Times Cited Count:6 Percentile:41.05(Engineering, Electrical & Electronic)

JAEA, as the JADA, signed PA for 9 ITER TF coil in 2008. The WP of the TF coil consists of seven DPs and each of DPs has a RP. The conductor is inserted in a groove of a RP and CP is welded to fix the conductor. Since flatness of 2 mm is required for a RP after welding of CPs, laser welding will be used. The tight tolerance of the CP, such as 0.3 mm, is necessary. Machining of a CP from a plate is technically promising method to satisfy the required tight tolerance. However, the machining is time consuming, resulting in penalty of high cost. Therefore, the authors study the feasibility of manufacture of a CP by new method to reduce the cost. A straight CP can be fabricated by hot-rolling and cold-drawing with sufficiently high accuracy, such as $$pm$$0.1 mm. In addition, the curved CP can be obtained by bending this straight CP with the accuracy of 0.3 mm. Thus, it is concluded that the feasibility of manufacture of the straight and curved CPs with high accuracy can be demonstrated. From these results, JAEA begins trial manufacture of the proto RP and CPs from 2009.

Journal Articles

Results of R&D on ITER-TF winding critical issues

Koizumi, Norikiyo; Nakajima, Hideo; Matsui, Kunihiro; Isono, Takaaki; Okuno, Kiyoshi; Takayanagi, Tadatoshi*; Kuno, Kazuo*; Senda, Ikuo*

IEEE Transactions on Applied Superconductivity, 18(2), p.475 - 478, 2008/06

 Times Cited Count:15 Percentile:63.26(Engineering, Electrical & Electronic)

ITER-TF coil is scaled up by about 3 times from TFMC, which was developed in ITER EDA and successfully tested in EU. New technical issues are initiated because of the scale-up. The major issues are feasibilities of high accuracy automatic winding, precise prediction of conductor elongation and/or shrinkage after heat treatment to transfer the conductor in narrow grove of radial plate. It is also necessary to develop insulation system, whose radiation resistance is enough to sustain irradiation in ITER TF coil and which enable vacuum impregnation in suitable duration, such as 24 h. The authors therefore develop one of major parts of automatic winding machine, bending roller head, and optimize TF winding shape to enable successive winding. In addition, the elongation of the TF conductors was evaluated in $$pm$$ 200 ppm after the heat treatment. Moreover, impregnation test of the conductor was performed. The test results indicate that it will take a several ten hours to impregnate TF double-pancake by the method developed in EDA.

Journal Articles

Laser-arc hybrid welding for the cover plate of ITER TF coil

Shiihara, Katsunori*; Makino, Yoshinobu*; Ogawa, Tsuyoshi*; Asai, Satoru*; Kanahara, Toshio*; Senda, Ikuo*; Okuno, Kiyoshi; Koizumi, Norikiyo; Matsui, Kunihiro

Proceedings of 26th International Congress on Applications of Lasers & Electro-Optics (ICALEO 2007) (CD-ROM), p.316 - 324, 2007/10

The toroidal field coil is manufactured as one of superconducting coil systems in the ITER. For welding the cover plate of TF coil, the prevention of the thermal effect on the coil and the deformation of the whole coil are required. Moreover, the application of high efficient welding is required in consideration for the productivity. Therefore, laser-arc hybrid welding process was investigated for the application to the cover plate welding, because its process is superior in the tolerance of the joint gap and the ease of the control for the heat input. In the experiment, it was confirmed that the application of laser-arc hybrid welding with the double gas shielding for high concentration arc and the filler wire for controlling the deposit amount is effective in the joint gap up to 0.8mm. Besides, twin spot laser head with the arc was developed in order to weld the both sides of cover plate simultaneously. By the optimization of welding condition for twin spot laser-arc hybrid welding process, it was confirmed to be effective in the prevention of the gap movement during welding and the acquisition of the proper penetration without the weld defect. Finally, the effectiveness of laser-arc hybrid welding for the welding deformation and the weldability on the quality was verified by the scale model test with the actual shape.

Journal Articles

Design and analysis of plasma position and shape control in superconducting tokamak JT-60SC

Matsukawa, Makoto; Ishida, Shinichi; Sakasai, Akira; Urata, Kazuhiro*; Senda, Ikuo*; Kurita, Genichi; Tamai, Hiroshi; Sakurai, Shinji; Miura, Yushi; Masaki, Kei; et al.

Fusion Engineering and Design, 66-68(1-4), p.703 - 708, 2003/09

 Times Cited Count:2 Percentile:19.75(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Revised version of tokamak transient simulation code SAFALY, 2

Senda, Ikuo*; Fujieda, Hirobumi; Neyatani, Yuzuru; Tada, Eisuke; Shoji, Teruaki

JAERI-Data/Code 2003-012, 73 Pages, 2003/07

JAERI-Data-Code-2003-012.pdf:3.45MB

The tokamak transient simulation code, named SAFALY, was revised recently and the sensitivity analyses on the parameters in the code were carried out. This report is composed of two volumes. The formulation and the parameters in modeling the plasma and in-vessel components are described in the first volume. In this second volume, the results of the sensitivity studies are reported. The sensitivity studies were performed in two steps. In the first step, the responses of plasmas in the occurrence of plasma disturbances were analyzed for various initial conditions. For each disturbance, the initial condition of the plasma, which gave the largest increase of the fusion power, was identified. In the second step, by using initial conditions derived in the first step, the sensitivities of plasma reactions with respect to variation of the parameters in SAFALY code were analyzed. In the analyses, the increase of the fueling, the increase of the plasma confinement improvement factor and the increase of the auxiliary heating power were considered as plasma disturbances.

JAEA Reports

Revised version of tokamak transient simulation code SAFALY, 1

Senda, Ikuo*; Fujieda, Hirobumi; Neyatani, Yuzuru; Tada, Eisuke; Shoji, Teruaki

JAERI-Data/Code 2003-008, 37 Pages, 2003/06

JAERI-Data-Code-2003-008.pdf:1.58MB

Tokamak transient simulation code, named SAFALY, was revised. SAFALY code has been developed to simulate transient events in Tokamaks. Modeling of the plasma and algorithms of the simulation were revised. The code was also modified to deal with the variation of the plasma current. The code was improved to allow flexible modeling of in-vessel components. The data transfer between SAFALY and related codes was arranged to prepare data required in analyses with SAFALY, such as the distributions of heat/neutron loads and the radiation form factor between in-vessel components. The report is composed of two volumes. The formulation and the parameters in modeling plasma and in-vessel components are described in this first volume. Examples of simulation results, using the design of ITER-FDR in 2001, are presented and general properties of plasmas' responses with respect to perturbations are discussed. The results of the sensitivity studies with respect to simulation parameters and initial conditions will be reported in the second volume.

Journal Articles

Linear evolution of plasma equilibrium in tokamaks

Senda, Ikuo; Shoji, Teruaki; Tsunematsu, Toshihide

Nuclear Fusion, 42(5), p.568 - 580, 2002/05

 Times Cited Count:4 Percentile:15.23(Physics, Fluids & Plasmas)

no abstracts in English

Journal Articles

The Summary report on engineering design activities in the International Thermonuclear Experimental Reactor (ITER) project

Mori, Masahiro; Shoji, Teruaki; Araki, Masanori; Saito, Keiji*; Senda, Ikuo; Omori, Junji*; Sato, Shinichi*; Inoue, Takashi; Ono, Isamu*; Kataoka, Takahiro*; et al.

Nihon Genshiryoku Gakkai-Shi, 44(1), p.16 - 89, 2002/01

no abstracts in English

Journal Articles

ITER engineering design

Shimomura, Yasuo; Tsunematsu, Toshihide; Yamamoto, Shin; Maruyama, So; Mizoguchi, Tadanori*; Takahashi, Yoshikazu; Yoshida, Kiyoshi; Kitamura, Kazunori*; Ioki, Kimihiro*; Inoue, Takashi; et al.

Purazuma, Kaku Yugo Gakkai-Shi, 78(Suppl.), 224 Pages, 2002/01

no abstracts in English

Journal Articles

Conceptual tokamak design at high neutron fluence

Araki, Masanori; Sato, Shinichi*; Senda, Ikuo; Omori, Junji*; Shoji, Teruaki

Fusion Engineering and Design, 58-59, p.887 - 892, 2001/11

 Times Cited Count:0 Percentile:0.01(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Performance assessment of ITER-FEAT

Murakami, Yoshiki*; Senda, Ikuo; Chudnovskiy, A.*; Vayakis, G.*; Polevoi, A. R.*; Shimada, Michiya

Purazuma, Kaku Yugo Gakkai-Shi, 73(7), p.712 - 729, 2001/07

no abstracts in English

Journal Articles

Design analysis on the magnetic field control system in compact ITER

Senda, Ikuo; Shoji, Teruaki; Araki, Masanori; ITER Japan Home Team; ITER Joint Central Team

International Journal of Applied Electromagnetics and Mechanics, 13(1-4), p.349 - 357, 2001/00

no abstracts in English

Journal Articles

Prototype tokamak fusion power reactor based on SiC/SiC composite material, focussing on easy maintenance

Nishio, Satoshi; Ueda, Shuzo; Kurihara, Ryoichi; Kuroda, Toshimasa*; Miura, H.*; Sako, Kiyoshi*; Takase, Kazuyuki; Seki, Yasushi; Adachi, Junichi*; Yamazaki, Seiichiro*; et al.

Fusion Engineering and Design, 48(3-4), p.271 - 279, 2000/09

 Times Cited Count:16 Percentile:72(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Simulation studies of plasma initiation and disruption in JT-60U

Senda, Ikuo*; Shoji, Teruaki; Tsunematsu, Toshihide; Matsukawa, Makoto; Ushigusa, Kenkichi

Nucl. Eng. Des., 45(1), p.15 - 29, 1999/00

no abstracts in English

Journal Articles

Optimization of plasma initiation in the ITER tokamak

Senda, Ikuo*; Shoji, Teruaki; Tsunematsu, Toshihide; *; Fujieda, Hirobumi*

Fusion Engineering and Design, 42, p.395 - 399, 1998/00

 Times Cited Count:3 Percentile:32.94(Nuclear Science & Technology)

no abstracts in English

Journal Articles

3-D electromagnetic transient characteristics of in-vessel components in tokamak reactor

Takase, Haruhiko; Senda, Ikuo; Araki, Masanori; Shoji, Teruaki; Tsunematsu, Toshihide

IAEA-CN-69/FTP/28, 4 Pages, 1998/00

no abstracts in English

Journal Articles

A Model of ions interacting with neutrals in high electric field and the application to presheath formations

Senda, Ikuo*

Physics of Plasmas, 4(5), p.1308 - 1315, 1997/05

 Times Cited Count:1 Percentile:4.29(Physics, Fluids & Plasmas)

no abstracts in English

Journal Articles

Approximation of eddy currents in three dimensional structures by toroidally symmetric models,and plasma control issues

Senda, Ikuo*; Shoji, Teruaki; Tsunematsu, Toshihide; *; Fujieda, Hirobumi*

Nuclear Fusion, 37(8), p.1129 - 1145, 1997/00

 Times Cited Count:9 Percentile:34.82(Physics, Fluids & Plasmas)

no abstracts in English

Journal Articles

Fast ion confinement in JT-60U and implications for ITER

Tobita, Kenji; Hamamatsu, Kiyotaka; Harano, Hideki*; Nishitani, Takeo; Kusama, Yoshinori; Kimura, Haruyuki; Takizuka, Tomonori; Fujieda, Hirobumi*; Shoji, Teruaki; Senda, Ikuo*; et al.

Proc. of 5th IAEA Technical Committee Meeting on Alpha Particles in Fusion Research, p.45 - 48, 1997/00

no abstracts in English

30 (Records 1-20 displayed on this page)