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Kataoka, Masaharu; Mukai, Masayuki; Sawaguchi, Takuma; Tsukada, Manabu; Kadowaki, Mitsushi*; Maeda, Toshikatsu; Tanaka, Tadao
no journal, ,
no abstracts in English
Uchikawa, Sadao; Nakano, Yoshihiro; Okubo, Tsutomu
no journal, ,
no abstracts in English
Shikaze, Yoshiaki; Tanimura, Yoshihiko; Tsutsumi, Masahiro; Yoshizawa, Michio
no journal, ,
no abstracts in English
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
Yamada, Fumiaki; Araki, Kosuke*
no journal, ,
There was not the influence that Monju system startup tests data gave to numerical analysis of large pipe break in primary heat transfer system concerned from comparison actual plant base analysis and before conservative base analysis.
Okusa, Kyoichi; Muranaka, Makoto; Sotsu, Masutake; Kimura, Koichi
no journal, ,
The ultrasonic thermometer is installed on the piping of the secondary cooling system in Monju. The characteristic of the ultrasonic thermometer in case of the sodium temperature change was evaluated as the first stage of system startup test of Monju. The evaluated temperature by the ultrasonic thermometer agreed well with the thermocouple measurement in this condition.
Takeyasu, Shinji; Takebayashi, Hiroyuki; Watanabe, Kazunori*; Shimizu, Takenori
no journal, ,
no abstracts in English
Nagai, Ryoji; Hajima, Ryoichi; Nishimori, Nobuyuki
no journal, ,
no abstracts in English
Onishi, Takashi; Osaka, Masahiko; Miwa, Shuhei; Obayashi, Hiroshi; Sekino, Hirotaka*; Kirishima, Akira*; Sato, Nobuaki*
no journal, ,
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*
no journal, ,
no abstracts in English
Sugiyama, Katsuteru*; Noguchi, Hiroki; Takegami, Hiroaki; Onuki, Kaoru; Kaneko, Akiko*; Abe, Yutaka*
no journal, ,
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
no journal, ,
no abstracts in English
Moriyama, Kiyofumi
no journal, ,
no abstracts in English