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Journal Articles

Unusual redox behavior of ruthenocene confined in the micropores of activated carbon

Itoi, Hiroyuki*; Ninomiya, Takeru*; Hasegawa, Hideyuki*; Maki, Shintaro*; Sakakibara, Akihiro*; Suzuki, Ryutaro*; Kasai, Yuto*; Iwata, Hiroyuki*; Matsumura, Daiju; Owada, Mao*; et al.

Journal of Physical Chemistry C, 124(28), p.15205 - 15215, 2020/07

 Times Cited Count:8 Percentile:39.3(Chemistry, Physical)

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

High-temperature continuous operation of the HTTR

Takamatsu, Kuniyoshi; Sawa, Kazuhiro; Kunitomi, Kazuhiko; Hino, Ryutaro; Ogawa, Masuro; Komori, Yoshihiro; Nakazawa, Toshio*; Iyoku, Tatsuo; Fujimoto, Nozomu; Nishihara, Tetsuo; et al.

Nihon Genshiryoku Gakkai Wabun Rombunshi, 10(4), p.290 - 300, 2011/12

A high temperature (950$$^{circ}$$C) continuous operation has been performed for 50 days on the HTTR from January to March in 2010, and the potential to supply stable heat of high temperature for hydrogen production for a long time was demonstrated for the first time in the world. This successful operation could establish technological basis of HTGRs and show potential of nuclear energy as heat source for innovative thermo-chemical-based hydrogen production, emitting greenhouse gases on a "low-carbon path" for the first time in the world.

JAEA Reports

Outline of operation and control system and analytical investigation of transient behavior of an out-of-pile hydrogen production system for HTTR heat utilization system

Inagaki, Yoshiyuki; Hada, Kazuhiko; Nishihara, Tetsuo; Takeda, Tetsuaki; Hino, Ryutaro; Haga, Katsuhiro

JAERI-Tech 97-050, 125 Pages, 1997/10

JAERI-Tech-97-050.pdf:2.96MB

no abstracts in English

Journal Articles

Out-of-pile demonstration test program of HTTR hydrogen production system by steam reforming of natural gas

Inagaki, Yoshiyuki; Hino, Ryutaro; Hada, Kazuhiko*; Haga, Katsuhiro; Nishihara, Tetsuo; Takeda, Tetsuaki; Shiozawa, Shusaku

Proc. of 5th Int. Conf. on Nucl. Eng. (ICONE-5)(CD-ROM), 5 Pages, 1997/00

no abstracts in English

JAEA Reports

Preliminary design of steam reformer in out-pile demonstration test facility for HTTR heat utilization system

Haga, Katsuhiro; Hino, Ryutaro; Inagaki, Yoshiyuki; Hada, Kazuhiko; ; ; Nishihara, Tetsuo; Yamada, Seiya*; Sudo, Yukio

JAERI-Tech 96-053, 71 Pages, 1996/11

JAERI-Tech-96-053.pdf:2.22MB

no abstracts in English

Oral presentation

Consideration for long-term storage of a spent zeolite adsorption vessel; Hydrogen diffusion analysis

Terada, Atsuhiko; Kamiji, Yu; Hino, Ryutaro; Nishihara, Kenji; Nagaishi, Ryuji; Yamagishi, Isao; Okagaki, Yuria*

no journal, , 

Japan Atomic Energy Agency has extensively conducted R&D on the management of secondary wastes produced by the operation of the system based on the Fukushima Daiichi research and development roadmap. In this paper, to comprehend the temperature distribution and hydrogen diffusion inside the spent zeolite vessel, we report thermal-hydraulic analytical results.

Oral presentation

Consideration for long-term storage of a spent zeolite adsorption vessel, 4; Hydrogen diffusion analysis

Terada, Atsuhiko; Kamiji, Yu; Sato, Hiroyuki; Nishihara, Kenji; Nagaishi, Ryuji; Morita, Keisuke; Yamagishi, Isao; Hino, Ryutaro

no journal, , 

no abstracts in English

Oral presentation

Development of numerical simulation method for relocation behavior of molten materials in nuclear reactors, 12; Measurement of the behavior of flow down liquid film

Hihara, Yutaro*; Monji, Hideaki*; Abe, Yutaka*; Yamashita, Susumu; Yoshida, Hiroyuki

no journal, , 

no abstracts in English

9 (Records 1-9 displayed on this page)
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