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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
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.
Tada, Hiroyuki*; Saito, Akira*; Nakaya, Atsushi*; Kumasaka, Hiroo*; Hayashi, Katsuhiko; Noguchi, Akira; Kishi, Hirokazu; Nakama, Shigeo
no journal, ,
Bending test of the segmental rings consist of staggered pieces of rocks bonded by low-pH mortar is conducted in order to identify the mechanical properties of rock segmental rings comparing with parallel arrangement. As a result, it was found that the maximum load was reached at 130 to 210 kN in the positive bending tests for staggered rock blocks, lower than 210 to 270 kN for rock blocks arranged in parallel. In the negative bending tests, on the other hand, the maximum load was reached at 30 to 40 kN, lower than a maximum load of 40 kN for the rock blocks arranged in parallel. The results thus varied. Cracks occurred along the interface between the rock block and mortar in the specimen for the blocks arranged in parallel. For the staggered rock blocks, cracks penetrated through the mortar and the rock block near the point of loading in the specimen. Thus, it was confirmed that cracking occurred in different manners.
Komoto, Norio; Sasaki, Hirofumi; Kawata, Tsuyoshi; Taki, Kiyotaka; Kinoshita, Shigemi*
no journal, ,
no abstracts in English
Terada, Kazushi*; Iwamoto, Nobuyuki
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no abstracts in English
Nagai, Haruyasu; Kobayashi, Takuya; Tsuzuki, Katsunori; Terada, Hiroaki
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no abstracts in English
Kofuji, Hirohide; Sawada, Nobuyuki*; Sasaki, Kazuya*; Amamoto, Ippei; Myochin, Munetaka; Suzuki, Akihiro*; Terai, Takayuki*
no journal, ,
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
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*
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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.
Suzuki, Mitsuru
no journal, ,
no abstracts in English