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Chiba, Satoshi; Ogata, Kazuyuki*; Hashimoto, Shintaro; Aritomo, Yoshihiro
no journal, ,
no abstracts in English
Kawagoe, Shinji; Higashiura, Norikazu; Goto, Tetsuo*
no journal, ,
no abstracts in English
Mo amount generated by irradiating natural Mo in JRR-3Komeda, Masao; Hirose, Akira; Sorita, Takami; Wada, Shigeru; Ishikawa, Koji*
no journal, ,
no abstracts in English
Ishii, Junichi; Kobayashi, Fuyumi; Uchida, Shoji; Sumiya, Masato; Umeda, Miki
no journal, ,
no abstracts in English
Udagawa, Yutaka; Yamaguchi, Masatake; Abe, Hiroaki*; Sekimura, Naoto*
no journal, ,
no abstracts in English
Yokoyama, Kaoru; Hata, Haruhi; Sugitsue, Noritake; Hyakutake, Toru*; Muto, Akinori*; Sasakura, Mariko*; Minowa, Hirotsugu*; Suzuki, Kazuhiko*
no journal, ,
The decontamination technique using the iodine heptafluoride is known as a system decontamination technique of facilities like the uranium enrichment plant where the uranium hexafluoride was handled. In this report, the mechanism of the system decontamination using the iodine heptafluoride is clarified at a molecular level. The generation process of the uranium tetrafluoride is estimated using the plant operation data. In addition, the generation speed of the uranium tetrafluoride and the activation energy are of the uranium tetrafluoride and iodine heptafluoride reaction are estimated.
Tc generated from natural-Mo(n,
)Mo, 4; Analysis in the verification test of the producing process of Tc milked from a highly radioactive MoSonoda, Takashi; Umeda, Miki; Tagami, Susumu; Kurobane, Shiro; Miyoshi, Yoshinori; Tanaka, Atsushi*; Ishikawa, Koji*; Tsuguchi, Akira*; Tatenuma, Katsuyoshi*
no journal, ,
no abstracts in English
/UO
redox potential in LiMoO
-NaMoO by absorption spectrometryNagai, Takayuki; Fukushima, Mineo; Myochin, Munetaka; Uehara, Akihiro*; Fujii, Toshiyuki*; Yamana, Hajimu*
no journal, ,
no abstracts in English
Katsurai, Kiyomichi; Washiya, Tadahiro; Onishi, Hiroyuki*; Kuroda, Kazuhiko*; Nishikawa, Hideaki*; Nakatani, Tatsuya*; Yamashita, Kazuhiko*; Yoshimine, Chihiro*
no journal, ,
This report presents the knowledge acquired by the endurance test of the bearing used for the rotary drum type continuation dissolver under development as part of Fast Breeder Reactor Cycle technology Development Project (FaCT project). The bearing used for a dissolver is used on high radiation environment and the severe conditions of high load low swing motion operation. In order to check the endurance of the bearing in such conditions, the endurance test of the small scale of hybrid roll bearing using the lubricant which imitated carbon slide bearing as a-less lubricous type, and imitated radiation and heat degradation as a lubricous type was carried out, and the applicability to dissolver bearing was evaluated.
Ikeuchi, Hirotomo; Shibata, Atsuhiro; Ouchi, Shinichi; Katsurai, Kiyomichi; Sano, Yuichi; Washiya, Tadahiro
no journal, ,
no abstracts in English
Kitawaki, Shinichi; Nakayoshi, Akira; Sakamura, Yoshiharu*; Akiyama, Naoyuki*
no journal, ,
no abstracts in English
Mizuno, Mineo; Sudo, Katsuo; Takeuchi, Kentaro; Okita, Takatoshi; Kihara, Yoshiyuki
no journal, ,
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*
no journal, ,
no abstracts in English
-ray beams; Simulation of -ray generation and detectionHajima, Ryoichi; Hayakawa, Takehito; Kikuzawa, Nobuhiro
no journal, ,
no abstracts in English
Komoto, Norio; Sasaki, Hirofumi; Kawata, Tsuyoshi; Taki, Kiyotaka; Kinoshita, Shigemi*
no journal, ,
no abstracts in English
Shibamoto, Yasuteru; Yonomoto, Taisuke; Maruyama, Yu
no journal, ,
no abstracts in English
Sato, Isamu; Katsuyama, Kozo; Arai, Yasuo
no journal, ,
To understand release behavior of He and fission gases from irradiated fuel, the quantities of He and fission gases accumulated in mixed oxide fuel irradiated in a fast reactor was measured to reveal retaining gas amounts per pin.
Koide, Masashi*; Saito, Takumi*; Nagasaki, Shinya*; Yamamoto, Yuhei; Mizuno, Takashi
no journal, ,
no abstracts in English
Sugino, Kazuteru; Ohgama, Kazuya; Nakazato, Wataru*; Moriwaki, Hiroyuki*
no journal, ,
Towards realizations of the demonstration reactor in around 2025 and the commercialized reactor in around 2050, a investigation on the conceptual core design of the sodium-cooled fast reactor (JSFR: Japan Sodium-cooled Fast Reactor) is under going. This paper presents the elavuation of the core design prediction accuracy based on the studies related to the latest nuclear data.
Shikaze, Yoshiaki; Tanimura, Yoshihiko; Tsutsumi, Masahiro; Yoshizawa, Michio
no journal, ,
no abstracts in English