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Journal Articles

Neutron emission profile measurement and fast charge exchange neutral particle flux measurement for transport analysis of energetic ions in JT-60U

Ishikawa, Masao; Nishitani, Takeo; Kusama, Yoshinori; Sukegawa, Atsuhiko; Takechi, Manabu; Shinohara, Koji; Krasilnikov, V. A.*; Kaschuck, Y.*; Sasao, Mamiko*; Isobe, Mitsutaka*; et al.

Plasma and Fusion Research (Internet), 2, p.019_1 - 019_11, 2007/05

no abstracts in English

Journal Articles

Development of integrated SOL/divertor code and simulation study in JAEA

Kawashima, Hisato; Shimizu, Katsuhiro; Takizuka, Tomonori; Sakurai, Shinji; Nakano, Tomohide; Asakura, Nobuyuki; Ozeki, Takahisa

Plasma and Fusion Research (Internet), 1(6), p.031_1 - 031_13, 2006/06

no abstracts in English

Journal Articles

Progress of the neutronics study on the ITER test blanket

Sato, Satoshi; Verzirov, Y. M.; Ochiai, Kentaro; Nishitani, Takeo

Purazuma, Kaku Yugo Gakkai-Shi, 82(5), p.306 - 315, 2006/05

no abstracts in English

Oral presentation

Dependence of the beam uniformity on the magnetic filter strength in a large Cs-seeded negative ion source for ITER

Seki, Takayoshi; Hanada, Masaya; Tobari, Hiroyuki; Inoue, Takashi; Takado, Naoyuki*; Mizuno, Takatoshi*; Hatayama, Akiyoshi*; Kashiwagi, Mieko; Taniguchi, Masaki; Watanabe, Kazuhiro; et al.

no journal, , 

no abstracts in English

Oral presentation

Design study of plasma stabilization plate on National Centralized Tokamak (NCT)

Suzuki, Yutaka; Sakurai, Shinji; Shibama, Yusuke; Matsukawa, Makoto; Tamai, Hiroshi; Oda, Yasushi*; Shimizu, Katsusuke*

no journal, , 

no abstracts in English

Oral presentation

Development of the plasma movie database system in JT-60

Sueoka, Michiharu; Kawamata, Yoichi; Kurihara, Kenichi

no journal, , 

no abstracts in English

Oral presentation

Spherical tokamak research from the viewpoint of reactor design study

Tobita, Kenji

no journal, , 

no abstracts in English

Oral presentation

Preparation of procurement for ITER TF coil

Sugimoto, Makoto; Kitamura, Kazunori; Hamada, Kazuya; Nakajima, Hideo; Okuno, Kiyoshi

no journal, , 

no abstracts in English

Oral presentation

Recent design of superconducting coils on national centralized tokamak

Tsuchiya, Katsuhiko; Kizu, Kaname; Ando, Toshinari*; Takahashi, Hiroyuki*; Matsukawa, Makoto; Tamai, Hiroshi; Miura, Yukitoshi

no journal, , 

no abstracts in English

Oral presentation

Observation of radiation behavior by using an IR imaging bolometer in the JT-60U tokamak

Parchamy, H.*; Peterson, B. J.*; Konoshima, Shigeru; Ashikawa, Naoko*

no journal, , 

Foil bolometers are standard magnetic fusion plasma diagnostics, by which the energy lost from the plasma can be detected through the heating of a thin metal foil. Imaging bolometers have been used in experiments to make time traces of radiation, in neutral beam injection heated discharges. In our case, the radiation is observed by a semi-tangentially viewing IR imaging bolometer in the JT-60U Tokamak, where a graphite-coated gold foil with a thickness of 2.5microns and an effective area of 9cm$$times$$7cm is used. The frame rate of this IR camera is 30Hz. Future calibration of the infrared imaging video bolometer will compensates for nonuniformities in the foil. We also improve the diagnostic by enabling the acquisition of 14bit digital data (compared with 8bit video data in the last campaign) and additional shielding for the IR camera against the magnetic field, neutrons and $$gamma$$ particles. The maximum brightness of the radiation from the plasma core during a disruption has been visible. The distribution of the radiation intensity in two dimensions (2D) could be inferred from the IR camera. These measurements yield a wealth of information on radiation behavior. The figure shows the intensity distribution of the black body radiation from the foil heated by the plasma radiation. Waveforms of the radiated power signal, shown in the bottom box, are processed with 0.1 second low pass filter for comparison with the imaging bolometer. This work was partly supported by Grants-in-Aid for Scientific Research of the JSPS, Nos.16560729/16082207.

Oral presentation

Effects of tensile and compressive strain on critical currents of Nb$$_{3}$$Al strand and cable-in-conduit conductor

Kizu, Kaname; Ando, Toshinari*; Okuno, Kiyoshi; Koizumi, Norikiyo; Shimada, Katsuhiro; Seo, Kazutaka*; Takahata, Kazuya*; Tamai, Hiroshi; Tsuchiya, Katsuhiko; Nishimura, Arata*; et al.

no journal, , 

no abstracts in English

Oral presentation

Study of the radiolysis for ITER cooling water at 14MeV neutron

Sato, Kazuyoshi; Neyatani, Yuzuru; Maruo, Takeshi; Mukai, Satoru*; Uchida, Shoji*; Soman, Yoshindo*

no journal, , 

no abstracts in English

Oral presentation

Development status of JT-60 remote experiment; Discharge parameters setting from remote-site

Totsuka, Toshiyuki; Sakata, Shinya; Iba, Katsuyuki*

no journal, , 

no abstracts in English

Oral presentation

Study of advanced LIDAR Thomson scattering diagnostics for burning plasmas

Hatae, Takaki; Nakatsuka, Masahiro*; Yoshida, Hidetsugu*; Naito, Osamu

no journal, , 

no abstracts in English

Oral presentation

Improvement of uniformity of negative ion beam in a Cs-seeded large negative ion source for ITER

Tobari, Hiroyuki; Seki, Takayoshi; Hanada, Masaya; Inoue, Takashi; Kashiwagi, Mieko; Taniguchi, Masaki; Dairaku, Masayuki; Watanabe, Kazuhiro; Sakamoto, Keishi

no journal, , 

no abstracts in English

Oral presentation

Present design activity of the national centralized tokamak facility

Tamai, Hiroshi; National Centralized Tokamak Design Team

no journal, , 

The mission of the National Centralized Tokamak(NCT) is to demonstrate a steady-state high-beta plasma control required for the economically and environmentally attractive DEMO, which aims at early realisation of a fusion reactor. NCT is also expected as a satellite tokamak besides ITER to perform the support research on the operation scenario optimisation and a study for physics issues. In this talk, a control scenario for a high-beta non-inductive current drive with a high bootstrap fraction in a low normalised collisionality and Larmor radius region will be presented. Recent engineering design of the main component such as the superconducting coils, vacuum chamber, and plasma-facing materials optimised for the realisation of high performance plasma characteristics is also presented.

Oral presentation

Results and issues on research of MHD mode induced by fast ions in JT-60U

Shinohara, Koji

no journal, , 

no abstracts in English

Oral presentation

Beam optics of MeV accelerator for ITER

Inoue, Takashi; Kashiwagi, Mieko; Taniguchi, Masaki; Dairaku, Masayuki; Hanada, Masaya; Watanabe, Kazuhiro; Sakamoto, Keishi

no journal, , 

A beamlet divergence angle of as low as 5 mrad was achieved at the ITER relevant beam enrgies ($$geq$$ 800 keV) and current densities ($$geq$$100 A/m$$^{2}$$). The perveance to obtain such high power beams were similar to that of ITER operation (1 MeV, 200 A/m$$^{2}$$). Thus, the result suggests validity of beam optics design of the ITER accelerator.

Oral presentation

A Conceptual design and advanced R&D program for DEMO NBI

Inoue, Takashi

no journal, , 

A fusion DEMO reactor requires NBI of high energy ($$geq$$ 1 MeV) for high power plasma heating and current drive. The NBI system for DEMO must fulfill other requirements such as (1) cw operation for 1 year, (2) low maintenance frequency ($$leq$$ once per year), (3) operability under radiation, (4) high system efficiency ($$geq$$ 50%). The present talk discusses DEMO NBI as a reasonable extrapolation of results from R&D and engineering design of the ITER NBI. For (1) and (2) above, R&D of filamentless source such as RF driven negative ion sources is in progress. The ITER R&D suggests possible extrapolation of exsisting electrostatic accelerator technologies up to 1.5 MeV. Additional radiation shielding is to be installed around the beam path, of which cross sectional area is reduced by merging multibeamlets into several beam groups. A concept of laser neutralizer, that utilizes semmiconductor lasers, is presented and discussed to achieve higher system efficiency close to 90%.

Oral presentation

Measurement of $$gamma$$-ray by $$^{4}$$He(d,$$gamma$$)reaction and its application for burning plasma diagnostics

Kubota, Naoyoshi; Ochiai, Kentaro; Taniike, Akira*; Kitamura, Akira*

no journal, , 

no abstracts in English

76 (Records 1-20 displayed on this page)