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Journal Articles

Characterization and storage of radioactive zeolite waste

Yamagishi, Isao; Nagaishi, Ryuji; Kato, Chiaki; Morita, Keisuke; Terada, Atsuhiko; Kamiji, Yu; Hino, Ryutaro; Sato, Hiroyuki; Nishihara, Kenji; Tsubata, Yasuhiro; et al.

Journal of Nuclear Science and Technology, 51(7-8), p.1044 - 1053, 2014/07

 Times Cited Count:19 Percentile:81.41(Nuclear Science & Technology)

For safe storage of zeolite wastes generated by treatment of radioactive saline water at the Fukushima Daiichi Nuclear Power Station, properties of the Herschelite adsorbent were studied and its adsorption vessel was evaluated for hydrogen production and corrosion. Hydrogen production depends on its water level and dissolved species because hydrogen is oxidized by radicals in water. It is possible to evaluate hydrogen production rate in Herschelite submerged in seawater or pure water by taking into account of the depth effect of the water. The reference vessel of decay heat 504 W with or without residual pure water was evaluated for the hydrogen concentration by thermal hydraulic analysis using obtained fundamental properties. Maximum hydrogen concentration was below the lower explosive limit (4 %). The steady-state corrosion potential of a stainless steel 316L increased with absorbed dose rate but its increase was repressed by the presence of Herschelite. At 750 Gy/h and $$<$$60$$^{circ}$$C which were values evaluated at the bottom of the vessel of 504 W, the localized corrosion of SUS316L contacted with Herschelite would not immediately occur under 20,000 ppm of Cl$$^{-}$$ concentration.

Journal Articles

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*; Muto, Takashi*; Kaneko, Osamu*; Kawahata, Kazuo*; Mito, Toshiyuki*; Ida, Katsumi*; Imagawa, Shinsaku*; et al.

Nuclear Fusion, 47(10), p.S668 - S676, 2007/10

 Times Cited Count:34 Percentile:73.64(Physics, Fluids & Plasmas)

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/fuelling 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 a combination of efficient pumping of the local island divertor function and core fuelling by pellet injection has realized a super dense core as high as 5$$times$$10$$^{20}$$ m$$^{-3}$$, 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 on average) are also highlighted. The progress of LHD experiments in these two years is overviewed by highlighting IDB, high-beta and long pulse.

Journal Articles

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

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 5$$times$$10$$^{20}$$m$$^{-3}$$, 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 $$beta$$ and long pulse.

Journal Articles

Visualization study of molten metal-water interaction by using neutron radiography

Mishima, Kaichiro*; Hibiki, Takashi*; *; *; Moriyama, Kiyofumi; Sugimoto, Jun

Proc. of Int. Seminar on Vapor Explosions and Explosive Eruptions, p.101 - 109, 1997/00

no abstracts in English

JAEA Reports

None

*; *; *; *; *; *; *

PNC TJ9124 97-009, 150 Pages, 1996/12

PNC-TJ9124-97-009.pdf:9.43MB

None

Journal Articles

Development of cryogenic vacuum window for ECH system

Yokokura, Kenji; Kasugai, Atsushi; Sakamoto, Keishi; Takahashi, Koji; Tsuneoka, Masaki; Yamamoto, Takumi; Imai, Tsuyoshi; Nagashima, Takashi; Saito, Yasushi*; *; et al.

Purazuma, Kaku Yugo Gakkai-Shi, 71(8), p.760 - 771, 1995/08

no abstracts in English

Journal Articles

High power tests of the cryogenic window for millimeter wave

Kasugai, Atsushi; Yokokura, Kenji; Sakamoto, Keishi; Tsuneoka, Masaki; Yamamoto, Takumi; Imai, Tsuyoshi; Saito, Yasushi*; *; *; Ebisawa, Katsuyuki*

Proceedings of the 19th International Conference on Infrared and Millimeter Waves, 0, p.295 - 296, 1994/00

no abstracts in English

JAEA Reports

None

Yurugi, M.*; *; Horie, Y.*; Fujiwara, Yasushi*

PNC TJ1449 92-006, 121 Pages, 1992/02

PNC-TJ1449-92-006.pdf:3.04MB

None

JAEA Reports

Conceptual design of Fusion Experimental Reactor(FER/ITER); Electron cyclotron wave system

Yamamoto, Takumi; Tsuneoka, Masaki; Sakamoto, Keishi; Kimura, Haruyuki; Nagashima, Takashi; *; Saito, Yasushi*; *; Ito, Yasuyuki*

JAERI-M 91-194, 41 Pages, 1991/11

JAERI-M-91-194.pdf:1.03MB

no abstracts in English

JAEA Reports

Conceptual design of Fusion Experimental Reactor(FER/ITER); Ion cyclotron wave system

Kimura, Haruyuki; Saigusa, Mikio; Saito, Yasushi*; *; Nagashima, Takashi; Fujii, Tsuneyuki; *; *; Fukuyama, Atsushi*; Yamagiwa, Mitsuru; et al.

JAERI-M 91-094, 89 Pages, 1991/06

JAERI-M-91-094.pdf:2.25MB

no abstracts in English

JAEA Reports

ITER neutral beam injection system; Japanese design proposal

Ohara, Yoshihiro; Tanaka, Shigeru; Akiba, Masato; Araki, Masanori; Fujisawa, Noboru; Hanada, Masaya; Inoue, Takashi; *; Mizuno, Makoto; Okumura, Yoshikazu; et al.

JAERI-M 91-052, 176 Pages, 1991/03

JAERI-M-91-052.pdf:4.07MB

no abstracts in English

Journal Articles

Maintenance of neutral beam injectors for ITER; Japanese proposal

Tanaka, Shigeru; Ohara, Yoshihiro; Akiba, Masato; Araki, Masanori; Hanada, Masaya; Inoue, Takashi; Mizuno, Makoto; Okumura, Yoshikazu; Seki, Masahiro; Watanabe, Kazuhiro; et al.

Fusion Engineering and Design, 18, p.507 - 515, 1991/00

 Times Cited Count:2 Percentile:31.86(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Neutronics of neutral beam injector for ITER; Japanese proposal

Inoue, Takashi; Akiba, Masato; Araki, Masanori; Hanada, Masaya; *; Mizuno, Makoto; Okumura, Yoshikazu; Ohara, Yoshihiro; Seki, Masahiro; Tanaka, Shigeru; et al.

Fusion Engineering and Design, 18, p.369 - 376, 1991/00

 Times Cited Count:3 Percentile:40.77(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Plunger design and RF leakage measurement of choke stub for JT-60 ICRF heating system

Kobayashi, Noriyuki; Kimura, Haruyuki; Saigusa, Mikio; Fujii, Tsuneyuki; Ikeda, Yoshitaka; Saito, Yasushi*

Fusion Engineering and Design, 12(4), p.481 - 491, 1990/07

 Times Cited Count:3 Percentile:40.32(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Japanese contributions to IAEA INTOR Workshop, Phase two A,Part 3; Chapter VII; Configuration and maintenance

Iida, Hiromasa; *; *; Adachi, Junichi*; *; *; Hamajima, Takataro*; Hatayama, Akiyoshi*; *; *; et al.

JAERI-M 88-011, 261 Pages, 1988/02

JAERI-M-88-011.pdf:6.44MB

no abstracts in English

Journal Articles

Lower hybrid current drive and heating for FER

Hatayama, Akiyoshi*; Sugihara, Masayoshi; *; Saito, Yasushi*; *;

14th European Conf. on Controlled Fusion and Plasma Physics, Vol. 11D, No. 3, p.1046 - 1049, 1987/00

no abstracts in English

16 (Records 1-16 displayed on this page)
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