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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
Hoshino, Takanori; Ikeuchi, Hirotomo; Sano, Yuichi; Watanabe, Masayuki; Suganuma, Takashi
no journal, ,
no abstracts in English
Sakamura, Yoshiharu*; Murakami, Tsuyoshi*; Akiyama, Naoyuki*; Kitawaki, Shinichi; Nakayoshi, Akira; Fukushima, Mineo
no journal, ,
no abstracts in English
Hata, Haruhi; Yokoyama, Kaoru; Sugitsue, Noritake; Hyakutake, Toru*; Muto, Akinori*; Sasakura, Mariko*; Minowa, Hirotsugu*; Suzuki, Kazuhiko*
no journal, ,
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.
Nakayama, Hiromasa; Nagai, Haruyasu
no journal, ,
We perform Large-Eddy Simulations (LES) on turbulent flows and plume dispersions within and over regular arrays of cubic buildings with various roughness densities and investigate the influence of the building arrangement pattern on the characteristics of mean and fluctuation concentrations for the assessment of human health hazard from toxic substances and the safety analysis of flammable gas.
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.
Nagai, Ryoji; Hajima, Ryoichi; Nishimori, Nobuyuki
no journal, ,
no abstracts in English
Yoshida, Hiroyuki; Suzuki, Takayuki*; Takase, Kazuyuki; Ikuta, Ryuhei*; Koizumi, Yasuo*
no journal, ,
no abstracts in English
Ikuta, Ryuhei*; Koizumi, Yasuo*; Yoshida, Hiroyuki; Takase, Kazuyuki
no journal, ,
no abstracts in English
Aoyama, Yasuo; Komuro, Michiyasu; Seki, Masakazu; Izawa, Kazuhiko; Sono, Hiroki; Ogawa, Kazuhiko; Yanagisawa, Hiroshi; Miyoshi, Yoshinori
no journal, ,
no abstracts in English
Kurisaka, Kenichi; Takamatsu, Misao; Martin, L.*
no journal, ,
This study aims to quantify the probability distribution of the leak flow rate when a sodium leak event takes place, in terms of the effectiveness evaluation of accident management measures using probabilistic safety assessment. For this purpose, sodium leak instances that were experienced in domestic and foreign sodium-cooled fast reactor systems were investigated and analyzed. In most of these leak instances, individual total leak amount is known, but the leak duration time is unknown. Therefore, the previous study needed to assume the leak duration time as a probability distribution to estimate the leak flow rate. In this study, for more realistic evaluation, we investigated both total leak amount and leak duration time of sodium leak instances that were experienced in the Phenix reactor system. For 12 instances where total leak amount was already known, leak duration time became clear. Five leak instances were newly added. The probability distribution of the leak duration time was statistically analyzed by using these data. As a result, it became possible to quantify more realistically the probability distribution of the leak flow rate.
Naruto, Kenichi*; Kurisaka, Kenichi
no journal, ,
This study aims to implement a probabilistic safety assessment (PSA) based on the component operating experience in sodium-cooled fast reactors (SFR). For this purpose, we developed the component reliability database for LMFBRs named CORDS and evaluated the failure rate for SFR PSA using CORDS. The reliability data of 33 years and 15 years have been accumulated in CORDS from Joyo and Monju, respectively. Baysian method was applied to the failure rate evaluation. This evaluation was classified into three cases by considering applicable data amount: (1) when sufficient data of the target plant is available, conventional Bayesian update was applied by using its own data and non-informative prior; (2) when sufficient data of similar plants is available, parametric empirical Baysian method was applied; (3) when sufficient data is not available, conventional Bayesian update was implemented by using all data. This study served to evaluate the failure rate for Monju PSA.
Ogino, Hideki; Hirano, Hiroyasu; Ishii, Hideyuki*; Sakamoto, Yukio*
no journal, ,
no abstracts in English
Ishii, Junichi; Kobayashi, Fuyumi; Uchida, Shoji; Sumiya, Masato; Umeda, Miki
no journal, ,
no abstracts in English