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Arakawa, Hiroyuki; Sasao, Hajime; Kawano, Yasunori; Itami, Kiyoshi
no journal, ,
no abstracts in English
Idomura, Yasuhiro
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Based on a first principle, full-f gyrokinetic simulations evolve equilibrium distribution and turbulent fluctuations simultaneously under a fixed input power as in the experiment. Recent Peta-scale supercomputers enabled numerical experiments over an energy confinement time scale, where plasma profiles are dictated based on a first principle model. In this talk, we present such long time scale simulations. Firstly, mechanisms to sustain steady profiles, in particular, intrinsic rotation profiles are addressed, and then, hysteresis properties of the heat diffusivity observed in modulated heating numerical experiments are discussed.
Oda, Yasuhisa; Ikeda, Ryosuke; Kajiwara, Ken; Oshima, Katsumi; Hayashi, Kazuo*; Takahashi, Koji; Sakamoto, Keishi; Purohito, D.*; Henderson, M.*
no journal, ,
no abstracts in English
Nagashima, Koji*; Yamaguchi, Tomoki*; Takii, Keita*; Sekiguchi, Kenji*; Saigusa, Mikio*; Oda, Yasuhisa; Fukunari, Masafumi*; Sakamoto, Keishi
no journal, ,
no abstracts in English
Takii, Keita*; Yamaguchi, Tomoki*; Nagashima, Koji*; Sekiguchi, Kenji*; Saigusa, Mikio*; Oda, Yasuhisa; Fukunari, Masafumi*; Sakamoto, Keishi
no journal, ,
no abstracts in English
Hatae, Takaki; Yatsuka, Eiichi; Bassan, M.*; Vayakis, G.*; Walsh, M.*; Itami, Kiyoshi
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no abstracts in English
Totsuka, Toshiyuki; Ozeki, Takahisa; Nakajima, Noriyoshi*; Matsukawa, Makoto
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A demonstration of remote experiment system using the JT-60SA is planned in March 2017. In this demonstration, feasibility of Remote Experiment System (RES) will be verified using JT-60SA in Naka from the ITER Remote Experiment Center (REC) of the International Fusion Energy Research Center (IFERC) located at Rokkasho in Aomori. RES provides the same experimental environment with that of JT-60SA control room to remote users of dedicated PC installed in REC room by accessing to the Remote Experiment Server (RESV) connected to a backbone-network of Naka fusion institute.
Kusama, Yoshinori
no journal, ,
no abstracts in English
Kamiya, Kensaku; Itami, Kiyoshi; Enokuchi, Akito*
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Design study of a wide-angle infrared thermography and visible observation diagnostics for JT-60SA are reported. In order to image a large section inside the vacuum vessel, the optical system of endoscope is to provide a wide-angle view in the IR and visible range, which is being designed with a field of view of 106 degrees vertical and 63 degrees horizontal. The estimated spatial resolution is better than a few cm at a distance of 8 m from the front optics with a slit diameter of 4 mm.
Shimada, Michiya; Hirooka, Yoshihiko*
no journal, ,
The use of circulating liquid metal is proposed to facilitate heat handling of the divertor, which is a very serious and challenging issue in fusion reactors. Two solid metal casings are placed where the separatrix magnetic surface hits. Each casing contains an electrode which can be biased positively or negatively with respect to the casing. The casing is filled with liquid metal like Ga, Sn or other metals with low melting point and low chemical activity. The j 
B force due to the radial current drives the poloidal motion of the liquid metal in such a way that the temperature rise at the separatrix hit point is kept at an acceptable level.
Okano, Fuminori; Masaki, Kei; Shibama, Yusuke; Yagyu, Junichi; Nishiyama, Tomokazu; Miyo, Yasuhiko; Kaminaga, Atsushi; Suzuki, Sadaaki; Nakamura, Shigetoshi; Sakasai, Akira; et al.
no journal, ,
no abstracts in English
Toma, Mitsunori; Hamamatsu, Kiyotaka; Hayashi, Nobuhiko; Honda, Mitsuru; Ide, Shunsuke
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no abstracts in English
Goto, Minoru; Nakagawa, Shigeaki; Matsuura, Hideaki*; Nakaya, Hiroyuki*; Katayama, Kazunari*
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A high temperature gas-cooled reactor (HTGR) is proposed as a tritium production device, which can produce a large amount of tritium by loading coated Li pebbles into the core without a major change of the original reactor core design. The engineering study was performed to clarify the problem of the tritium production system and assess the possibility of the resolution. As a result, it was assessed that all of the problems could be resolved from an engineering view point by using the HTTR (High Temperature engineering Test Reactor) experiences on the production of the coated fuel particles and deal of the fuels.
Imazawa, Ryota; Kawano, Yasunori; Itami, Kiyoshi
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no abstracts in English
Ikeda, Yoshitaka; Fusion For Energy*
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The content of the "Start of Assembly of JT-60SA and the Project Schedule" is presented in the symposium of "EU & JA Collaborative Activities and Joint Exploitation Strategy towards JT-60SA Experiment". The main content is as follows; The JT-60SA project is one of the three projects of the Broader Approach activities being undertaken jointly by Japan and Europe. There are two Implementing Agencies (IAs) such as the Japan Atomic Energy Agency (JAEA) for Japan, and Fusion for Energy (F4E) for Europe. Both JAEA and F4E share the procurements and services to produce its first plasma in March 2019. Thanks to good progress on both IA's contributions, the assembly of JT-60SA started at Naka site in January 2013, with the arrival of the cryostat base from Europe after disassembly of JT-60. The assembly of the JT-60SA, which is featured by the integration process to combine the key components contributed by both IAs, is underway to produce its first plasma in March 2019.
Hasegawa, Koichi; Arai, Takashi; Hoshi, Ryo; Masaki, Kei; Saeki, Hisashi; Sakata, Shinya; Sawai, Hiroaki; Shibanuma, Kiyoshi; Suzuki, Sadaaki; Tsukao, Naohiro; et al.
no journal, ,
JAEA pushes forward construction of superconduction tokamak (JT-60SA) as part of Broader Approach activity in cooperation with EU. JT-60SA is concentrated and highly precise with a large structure in the limited space, and it is necessary to assemble it. Therefore, from 2007, assembling examination using the 3D CAD has been performed. By this lecture introduce the examination situation of the assembling procedures such as TF coil, a vacuum vessel, cryostat, EF coil of JT-60SA.
Ishikawa, Masao; Kondoh, Takashi; Takeda, Keigo*; Itami, Kiyoshi
no journal, ,
The Microfission chamber (MFC) diagnostics measure the total neutron emission from DT plasmas, providing the evaluation of the fusion power in ITER and the MFC is procured by JAEA. At the present stage, designs, tests and analyses have been performed as preliminary design for "In-vessel Components of ITER MFC System". For Design, detail design of feed through and making installation procedure of the MFC detectors and cable connectors. Also, thermal cycle test of the signal cable and noise test of signal transmission system have been performed. Further, thermal and EM analysis for in-vessel components have been done. In this conference, details of these activities are presented.
Ito, Yuzuru; Wakai, Eiichi
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no abstracts in English
Takeuchi, Masaki; Sugie, Tatsuo; Takeyama, Shigeharu; Ogawa, Hiroaki; Itami, Kiyoshi
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In ITER, divertor IR thermography for measurement of surface temperature on divertor plates with high resolutions in both time and space has been designed by Japan. One of the issues is in-situ calibration of emissivity in IR light on the divertor plates, because the emissivity will change due to changes in surface properties caused by depositions and erosions. However, the in-situ calibration method has not been established yet. We recently conceived a new calibration method that an IR laser (quantum cascade laser) is irradiated to an observation surface and the emissivity will be evaluated from the scatter light. Therefore, laboratory experiments for development of calibration methods have been performed by using the components such as IR camera, heater, IR laser, black body source.
Yagyu, Junichi; Masaki, Kei; Suzuki, Sadaaki; Nishiyama, Tomokazu; Nakamura, Shigetoshi; Saeki, Hisashi; Hoshi, Ryo; Sawai, Hiroaki; Hasegawa, Koichi; Arai, Takashi; et al.
no journal, ,
no abstracts in English