JOPSS - Search Results

In International Business Forum for Fusion/Fission Energy 2009 held in Sapporo (Sapporo convention center, 7 to 9 on September in 2009), the recent status of ITER procurements in Japan and exhibition of ITER and BA activities were presented. Also, in Mechanical Engineering Congress 2009 Japan held in Morioka (Iwate Univ. 13-16 Sept.) and 2009 Anural Meeting of Atomic Energy Society of Japan held in Sendai (Tohoku Univ. 16-18 Sept.), the exhibition of ITER activities was presented. These were good opportunity for the PR for the ITER project as JAEA.

Journal Articles

Information on ITER project, 8

Ando, Toshiro

Purazuma, Kaku Yugo Gakkai-Shi, 84(3), P. 164, 2008/03

http://www.jspf.or.jp/Journal/PDF_JSPF/jspf2008_03/jspf2008_03-164.pdf

no abstracts in English

Journal Articles

Information on ITER project, 7

Ando, Toshiro

Purazuma, Kaku Yugo Gakkai-Shi, 84(1), P. 69, 2008/01

http://www.jspf.or.jp/Journal/PDF_JSPF/jspf2008_01/jspf2008_01-69.pdf

no abstracts in English

Journal Articles

Information on ITER project, 5

Ando, Toshiro

Purazuma, Kaku Yugo Gakkai-Shi, 83(9), P. 775, 2007/09

http://www.jspf.or.jp/Journal/PDF_JSPF/jspf2007_09/jspf2007_09-775.pdf

no abstracts in English

Journal Articles

Information on ITER project, 3

Ando, Toshiro

Purazuma, Kaku Yugo Gakkai-Shi, 83(5), P. 533, 2007/05

http://www.jspf.or.jp/Journal/PDF_JSPF/jspf2007_05/jspf2007_05-533.pdf

no abstracts in English

Journal Articles

Information on ITER project, 2

Ando, Toshiro

Purazuma, Kaku Yugo Gakkai-Shi, 83(3), P. 308, 2007/03

http://www.jspf.or.jp/Journal/PDF_JSPF/jspf2007_03/jspf2007_03-308.pdf

no abstracts in English

Journal Articles

Wall conditioning and experience of the carbon-based first wall in JT-60U

Masaki, Kei; Yagyu, Junichi; Arai, Takashi; Kaminaga, Atsushi; Kodama, Kozo; Miya, Naoyuki; Ando, Toshiro; Hiratsuka, Hajime; Saido, Masahiro

Fusion Science and Technology (JT-60 Special Issue), 42(2-3), p.386 - 395, 2002/09

https://doi.org/10.13182/FST02-A235

Times Cited Count：9 Percentile：51.46(Nuclear Science & Technology)

The wall conditioning of JT-60U consists of the 300 $^{circ}$ C baking, He-TDC, He-GDC, tokamak discharge cleaning and boronization. Using these methods, total pressure of the vacuum vessel reached finally 10 $^{-6}$ 10 $^{-5}$ Pa. The oxygen impurity was decreased to 0.5%. The experience with the carbon-based first wall showed that taper shaping is effective to reduce the local heat concentration to the tile edges. The observed poloidal asymmetric deposition of carbon on the divertor region implies that the carbon impurity produced in the outer divertor contributes to the deposition on the inner divertor. In 1992 and 1993, the B $_{4}$ C converted CFC tiles were installed in the outer divertor to reduce chemical sputtering of CFC tiles and oxygen impurity. The reduction was successfully demonstrated with the B $_{4}$ C converted CFC tiles. In order to understand the tritium behavior in JT-60U, tritium in the first wall and the exhaust gas were measured. The estimated tritium inventory in the first wall was 50% of the generated tritium.

Journal Articles

Development and operational experiences of the JT-60U tokamak and power supplies

Hosogane, Nobuyuki; Ninomiya, Hiromasa; Matsukawa, Makoto; Ando, Toshiro; Neyatani, Yuzuru; Horiike, Hiroshi*; Sakurai, Shinji; Masaki, Kei; Yamamoto, Masahiro; Kodama, Kozo; et al.

Fusion Science and Technology (JT-60 Special Issue), 42(2-3), p.368 - 385, 2002/09

https://doi.org/10.13182/FST02-A234

Times Cited Count：2 Percentile：17.03(Nuclear Science & Technology)

This paper reviews developments of the JT-60U tokamak and coil power supplies and their operational experiences obtained to date. The JT-60U is a large tokamak upgraded from the original JT-60 to obtain high plasma current, large plasma volume and highly elongated divertor configurations. In the modification, all components inside the bore of toroidal magnetic field coils, a vacuum vessel, poloidal magnetic field coils (PF-coils), divertor etc., were renewed. Furthermore, boron carbide converted CFC tiles were used as divertor tiles to reduce erosion of carbon-base tiles. Later, a semi-closed divertor with pumps was installed in the replacement of the open divertor. Various technologies and ideas introduced to develop these components their operational experiences provide important data for designing future tokamaks. Also, major troubles that had influence on the JT-60U operations are described. As a maintenance issue for tokamaks using deuterium fueling gas, a method for reducing radiation exposure of in-vessel workers are introduced.

Journal Articles