Progress in physics and technology developments for the modification of JT-60

Tamai, Hiroshi; Matsukawa, Makoto; Kurita, Genichi; Hayashi, Nobuhiko; Urata, Kazuhiro*; Miura, Yushi; Kizu, Kaname; Tsuchiya, Katsuhiko; Morioka, Atsuhiko; Kudo, Yusuke; et al.

Plasma Science and Technology, 6(1), p.2141 - 2150, 2004/02

https://doi.org/10.1088/1009-0630/6/1/006

The dominant issue for the the modification program of JT-60 (JT-60SC) is to demonstrate the steady state reactor relevant plasma operation. Physics design on plasma parameters, operation scenarios, and the plasma control method are investigated for the achievement of high-. Engineering design and the R&D on the superconducting magnet coils, radiation shield, and vacuum vessel are performed. Recent progress in such physics and technology developments is presented.

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

https://doi.org/10.1088/0029-5515/43/7/314

no abstracts in English

Research activities on Tokamaks in Japan; JT-60U, JFT-2M and TRIAM-1M

Ninomiya, Hiromasa; Kitsunezaki, Akio; Shimizu, Masatsugu; Kuriyama, Masaaki; JT-60 Team; Kimura, Haruyuki; Kawashima, Hisato; Tsuzuki, Kazuhiro; Sato, Masayasu; Isei, Nobuaki; et al.

Fusion Science and Technology, 42(1), p.7 - 31, 2002/07

https://doi.org/10.13182/FST02-A210

In order to establish scientific basis for the sustainment of highly integrated performance required in the advanced steady-state operation, JT-60U has been optimizing the discharge control scenarios of improved confinement plasmas and expanding the operation regions. Promising results toward the steady-state tokamak were obtained. The detail of such results is reported. JFT-2M has performed advanced and basic research for the development of high performance tokamak plasma as well as the structural material for a fusion reactor. The toroidal ripple reduction with ferritic steel plates outside the vacuum vessel was successfully demonstrated. No adverse effects were observed in the pre-testing on compatibility between ferritic steel plates, covering ~20% of the inside wall of the vacuum vessel, and plasma. The results of TRIAM-1M is also reported.

Development of the module inspection system for new standarized radiation monitoring modules

; Shimizu, Kazuaki; ; Chida, Toru; Mizugaki, Toshio; Oi, Yoshihiro

JAERI-Tech 94-023, 106 Pages, 1994/10

JAERI-Tech-94-023.pdf:3.43MB

no abstracts in English

A Multi-channel analyzer using a dedicated CAMAC memory

; ; ; ; ;

IEEE Transactions on Nuclear Science, NS-26(1), p.746 - 749, 1979/00

no abstracts in English

Development for practical use of intruder automated monitoring system

Tanuma, Koji; Hiruta, Toshihito; Kimura, Naoyuki; Shimizu, Kazuaki; Suzuki, Mitsutoshi; Ito, Toru

no journal, , 

JAEA is developing practical use of an intruder automated monitoring system aimed at early detection of intruders or suspicious objects entering into a site boundary or protected areas, etc. The system is aimed at rationalization and efficiency of guard functions by using monitoring camera and image analysis software to watch the action of intruder or suspicious individual. This paper introduces the results of comparative investigations, including the performance and function of intrusion detection, expansion of the system, the test results of environmental resistance over a long period of time (ex. climate conditions, small animals, weeds, behavior of intruders, etc.). The effectiveness of the monitoring system as a physical protection measure, and the scope of application other than nuclear facility are evaluated using typical foreign image analysis software.