Fabrication process qualification of TF Insert Coil using real ITER TF conductor

Ozeki, Hidemasa; Isono, Takaaki; Kawano, Katsumi; Saito, Toru; Kawasaki, Tsutomu; Nishino, Katsumi; Okuno, Kiyoshi; Kido, Shuichi*; Semba, Tomoyuki*; Suzuki, Yozo*; et al.

IEEE Transactions on Applied Superconductivity, 25(3), p.4200804_1 - 4200804_4, 2015/06

https://doi.org/10.1109/TASC.2014.2364393

Extended steady-state and high-beta regimes of net-current free heliotron plasmas in the large helical device

Motojima, Osamu*; Yamada, Hiroshi*; Komori, Akio*; Oyabu, Nobuyoshi*; Kaneko, Osamu*; Kawahata, Kazuo*; Mito, Toshiyuki*; Muto, Takashi*; Ida, Katsumi*; Imagawa, Shinsaku*; et al.

Proceedings of 21st IAEA Fusion Energy Conference (FEC 2006) (CD-ROM), 12 Pages, 2007/03

http://www-naweb.iaea.org/napc/physics/FEC/FEC2006/html/node31.htm#5947

The performance of net-current free Heliotron plasmas has been developed by findings of innovative operational scenarios in conjunction with an upgrade of the heating power and the pumping/fueling capability in the Large Helical Device (LHD). Consequently, the operational regime has been extended, in particular, with regard to high density, long pulse length and high beta. Diversified studies in LHD have elucidated the advantages of net-current free heliotron plasmas. In particular, an Internal Diffusion Barrier (IDB) by combination of efficient pumping of the local island divertor function and core fueling by pellet injection has realized a super dense core as high as 510m, which stimulates an attractive super dense core reactor. Achievements of a volume averaged beta of 4.5 % and a discharge duration of 54-min. with a total input energy of 1.6 GJ (490 kW in average) are also highlighted. The progress of LHD experiments in these two years is overviewed with highlighting IDB, high and long pulse.

Progress in JT-60 joint research

Kimura, Haruyuki; Inutake, Masaaki*; Kikuchi, Mitsuru; Ogawa, Yuichi*; Kamada, Yutaka; Ozeki, Takahisa; Naito, Osamu; Takase, Yuichi*; Ide, Shunsuke; Nagasaki, Kazunobu*; et al.

Purazuma, Kaku Yugo Gakkai-Shi, 83(1), p.81 - 93, 2007/01

http://ci.nii.ac.jp/naid/110006282206

no abstracts in English

Report of ITPA (International Tokamak Physics Activity) meeting, 13

Kawano, Yasunori; Kawahata, Kazuo*; Kusama, Yoshinori; Sasao, Mamiko*; Sugie, Tatsuo; Mase, Atsushi*; Asakura, Nobuyuki; Kato, Takako*; Takamura, Shuichi*; Tanabe, Tetsuo*; et al.

Purazuma, Kaku Yugo Gakkai-Shi, 81(2), p.128 - 130, 2005/02

http://ci.nii.ac.jp/naid/40006649327

no abstracts in English

Power loading on the beamline components and beam divergence of the negative-ion based NBI system for JT-60U

Hu, L.*; Akino, Noboru; Ebisawa, Noboru; Honda, Atsushi; Ito, Takao; Kawai, Mikito; Kazawa, Minoru; Kuriyama, Masaaki; Kusaka, Makoto*; Mogaki, Kazuhiko; et al.

JAERI-Tech 99-057, 16 Pages, 1999/08

JAERI-Tech-99-057.pdf:1.03MB

no abstracts in English

Examination of cyclic voltammetry of molten borosilicate glass

Nagai, Takayuki; Nishizawa, Daiji; Inose, Takehiko*; Sato, Seiichi*; Hatakeyama, Kiyoshi*; Seki, Katsumi*; Oyama, Koichi; Kano, Shigeru

no journal, , 

no abstracts in English

Fabrication of a test coil to evaluate performance of ITER conductor

Isono, Takaaki; Kawano, Katsumi; Ozeki, Hidemasa; Sato, Minoru; Saito, Toru; Nishino, Katsumi

no journal, , 

Japan Atomic Energy Agency (JAEA) has fabricated a test coil to evaluate superconducting performance of the conductor used for Central Solenoid (CS) of the International Thermonuclear Experimental Reactor (ITER) system. The coil is a 9-turn single layer solenoid coil with a 1.5-m diameter and will be inserted and tested in the Central Solenoid Model Coil (CSMC) test facility in JAEA. The conductor is cable-in-conduit type and has a square shape of 49 mm. The cable is composed of 576 NbSn strands and 288 copper strands. The conductor will be operated at 13-T magnetic field and 40 kA operating current. Fabrication sequence of the coil is; (1) winding of 1.5 m diameter, (2) fabrication of terminals, (3) heat treatment to generate superconductor, (4) turn insulation, (5) ground insulation, (6) assemble of structures and (7) installation of instruments. Before fabrication of the coil, trial coil was fabricated using a dummy conductor to demonstrate fabrication procedure. Fabrication results of trial and the test coil will be presented.

Redox behavior of RuO particles in borosilicate glass melts

Nagai, Takayuki; Inose, Takehiko*; Sato, Seiichi*; Hatakeyama, Kiyoshi*; Seki, Katsumi*

no journal, , 

no abstracts in English

Redox behavior of cerium and iron in molten borosilicate glass

Nagai, Takayuki; Kobayashi, Hidekazu; Okamoto, Yoshihiro; Inose, Takehiko*; Sato, Seiichi*; Hatakeyama, Kiyoshi*; Seki, Katsumi*

no journal, , 

no abstracts in English

Test results of CS insert for ITER; Test method

Isono, Takaaki; Kawano, Katsumi; Ozeki, Hidemasa; Saito, Toru; Nabara, Yoshihiro; Suwa, Tomone; Shimono, Mitsugu; Ebisawa, Noboru; Sato, Minoru; Uno, Yasuhiro; et al.

no journal, , 

JAEA is procuring conductors for ITER Central Solenoid (CS) and has evaluated its superconducting performance using CS Model Coil Test facility. We measured Tcs values during cyclic charge of 16,000 cycles and warm-up and cool-down cycle of 3 times. And we measured effect of coil deformation by electro-magnetic force on Tcs values and performed quench test. In this presentation, test method will be reported.