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Isozaki, Toshihiko; Tsutagi, Koichi; Shirato, Yoji; Nakazawa, Yutaka; Kake, Yasuhiro; Furukawa, Shinichi
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no abstracts in English
Morimoto, Yasuyuki; Tanaka, Yoshio; Takahashi, Nobuo; Tokuyasu, Takashi; Sugitsue, Noritake
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no abstracts in English
Nishimori, Nobuyuki; Nagai, Ryoji; Hajima, Ryoichi; Yamamoto, Masahiro*; Miyajima, Tsukasa*; Honda, Yosuke*; Kuriki, Masao*; Iijima, Hokuto*; Kuwahara, Makoto*; Okumi, Shoji*; et al.
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no abstracts in English
Ohara, Takaharu; Ikeda, Makinori; Morishita, Masaki; Miyazaki, Masashi; Shimada, Koji; Moriizumi, Makoto*
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no abstracts in English
Harada, Tatsuyuki*; Okafuji, Takashi*; Morishita, Masaki; Tsukimori, Kazuyuki
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no abstracts in English
Omae, Takahiro; Kato, Masaaki*; Kanayama, Haruyuki*; Morishita, Masaki
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no abstracts in English
Mizuno, Mineo; Sudo, Katsuo; Takeuchi, Kentaro; Okita, Takatoshi; Kihara, Yoshiyuki
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The short process is considered to be a main concept which has high feasibility in Fast Reactor Cycle Technology Development (FaCT). In this study, a small-scale fabrication test was carried out to investigate characteristic of MOX pellet made of granulated MOX powder blended with dry-route recycle powder, for the first time, as a basic test concern with the short process. As the results, it was found that the sintered density of the pellet clearly depends on the preparing conditions and content of recycle powder. The results is intended to be utilized in the investigation of engineering-scale test conditions.
-ray NDA experiment at the Compact ERLHajima, Ryoichi; Hayakawa, Takehito; Seya, Michio; Kawata, Hiroshi*; Kobayashi, Yukinori*; Urakawa, Junji*
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no abstracts in English
-ray beams; Simulation of -ray generation and detectionHajima, Ryoichi; Hayakawa, Takehito; Kikuzawa, Nobuhiro
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no abstracts in English
Kofuji, Hirohide; Sawada, Nobuyuki*; Sasaki, Kazuya*; Amamoto, Ippei; Myochin, Munetaka; Suzuki, Akihiro*; Terai, Takayuki*
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The phosphate conversion process has been studied for reuse of spent electrolyte generated from pyrochemical reprocessing. As the fundamental information of thermodynamic data, heat capacities of some kind of phosphate were measured and phosphate conversion reactions were discussed based on such thermodynamic data.
Kunimaru, Takanori; Hama, Katsuhiro; Ogata, Nobuhisa; Sato, Toshinori; Saegusa, Hiromitsu; Tsuruta, Tadahiko; Takeuchi, Ryuji; Matsuoka, Toshiyuki; Mizuno, Takashi
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no abstracts in English
Onishi, Takashi; Osaka, Masahiko; Miwa, Shuhei; Obayashi, Hiroshi; Sekino, Hirotaka*; Kirishima, Akira*; Sato, Nobuaki*
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As a demonstration of nuclear fuel reprocessing by sulfurization reaction, voloxidation, selective sulfurization and selective dissolution of simulated spent nuclear fuel pellet fabricated from U, Pu, Am and non-radioactive FP were conducted. As results, dissolution rate of each elements were obtained and behavior of MA and FP were investigated.
Maekawa, Keisuke; Inagaki, Manabu*; Tanaka, Tatsuya*; Hashimoto, Shuji*; Matsuo, Shigeaki*
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no abstracts in English
Sugiyama, Katsuteru*; Noguchi, Hiroki; Takegami, Hiroaki; Onuki, Kaoru; Kaneko, Akiko*; Abe, Yutaka*
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The Japan Atomic Energy Agency has been conducting R&D on thermo-chemical IS process, which is one of most attractive water-splitting hydrogen production methods using nuclear heat of a high temperature gas-cooled reactor. The present study concerns with development of IS process equipment utilizing direct contact heat exchanger (DCHX). The application of DCHX to the sulfuric acid decomposition step of IS process has been proposed such that the decomposed gas contacts with the sulfuric acid solution supplied from the Bunsen reaction step. The concept is very attractive in terms of the development of compact and efficient sulfuric acid concentrator. However, little is known on the behavior of sulfuric acid in the DCHX, which is required for the equipment design. Therefore, we considered an experimental acquisition of essential design parameter of the DCHX, the gas-phase mass transfer coefficient.
Morikawa, Keita; Kunimaru, Takanori
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Sato, Shinichiro; Sai, Hitoshi*; Oshima, Takeshi; Imaizumi, Mitsuru*; Shimazaki, Kazunori*; Kondo, Michio*
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no abstracts in English
Tanaka, Yoshio; Morimoto, Yasuyuki; Tokuyasu, Takashi; Takahashi, Nobuo; Sugitsue, Noritake
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In Ningyo-toge environmental engineering center started the decommissioning project of commercial-scale nuclear fuel facility in 2008. We worked on dismantling/removal of equipments in the radiation controlled area, and about 80 % were finished. Therefore, we arranged it systematically for dismantling work in work elements to need for the decommissioning project. The man-hour ratio of 3 work division was preparation 29 % and dismantlement 59 %, post-processing 12 %. The breakdown of each work division is preparations 14 processes and dismantlement 32, post-processing 11. At least 57 processes classifications are necessary for dismantling work. In addition, a man-hour ratio to need for post-processing was almost a constant in every result. On the other hand, the man-hour ratios of preparations and dismantling were classified in 3 groups.
Kushida, Noriyuki; Fujibayashi, Kenichi; Kureta, Masatoshi; Segawa, Mariko; Shinohara, Takenao; Takemiya, Hiroshi
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Center for Computational Science and E-systems of Japan Atomic Energy Agency has been developing elemental technologies for high-speed data analysis in order to achieve "On Site" data analysis. Recent huge experimental facilities provide tremendous amount of data, which is beyond traditional computers capability. Therefore we developed and applied novel parallel computing techniques. As a result, we achieved around 100 times speed-up in computation, and 10 times speed-up in data storage access than traditional computers.
Okano, Masanori; Goto, Yuichi; Jitsukata, Shu*; Nemoto, Hirokazu*; Kuno, Takehiko; Yamada, Keiji
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no abstracts in English
Hata, Haruhi; Yokoyama, Kaoru; Sugitsue, Noritake; Hyakutake, Toru*; Muto, Akinori*; Sasakura, Mariko*; Minowa, Hirotsugu*; Suzuki, Kazuhiko*
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As a first step to elucidate the molecular mechanism of decontamination systems for iodine heptafluoride, uranium hexafluoride and the metal (iron), the possibility of physical adsorption and chemical reactions with uranium hexafluoride and uranium tetrafluoride (solid), we investigate the possibility of physical adsorption and chemical reactions of this. Therefore, the intermolecular of uranium hexafluorides, iron and uranium hexafluoride, uranium tetrafluoride and uranium hexafluoride (solid) and evaluated by molecular orbital method to the intermolecular potential between, based on this data, MD law adhesion mechanism was estimated by uranium hexafluoride.