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Takeuchi, Masayuki; Onose, Tsutomu*; Obu, Yuichi*; Arai, Yoichi; Washiya, Tadahiro; Kitajima, Takafumi; Koizumi, Tsutomu
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no abstracts in English
Takeuchi, Masayuki; Onose, Tsutomu*; Fujisaku, Kazuhiko*; Arai, Yoichi; Washiya, Tadahiro; Kitajima, Takafumi; Koizumi, Tsutomu
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no abstracts in English
-ray irradiation test on magnetic bearing systemArai, Yoichi; Fujisaku, Kazuhiko*; Koizumi, Satoshi*; Takeuchi, Masayuki; Washiya, Tadahiro; Kitajima, Takafumi; Koizumi, Tsutomu
no journal, ,
no abstracts in English
Aose, Shinichi; Ogasawara, Koji; Nomura, Kazunori; Miyachi, Shigehiko; Ichige, Yoshiaki; Shinozaki, Tadahiro; Ouchi, Shinichi; Kitajima, Takafumi
no journal, ,
no abstracts in English
Aose, Shinichi; Kitajima, Takafumi; Ogasawara, Koji; Nomura, Kazunori; Miyachi, Shigehiko; Ichige, Yoshiaki; Shinozaki, Tadahiro; Ouchi, Shinichi; Nabemoto, Toyonobu*; Katahira, Fujio*; et al.
no journal, ,
no abstracts in English
Kaji, Naoya; Nakahara, Masaumi; Nakamura, Kazuhito; Shibata, Atsuhiro; Tomita, Yutaka; Washiya, Tadahiro; Kitajima, Takafumi; Koizumi, Tsutomu
no journal, ,
Solubility obtained from the latest crystallization tests using irradiated fuel and the tests implemented before using U or Pu/U are compared with the data showed by Hart. Based on the result, availability of the data to estimate crystallization ratio is considered.
Hinai, Hiroshi; Tomita, Yutaka; Nomura, Kazunori; Oyama, Koichi; Kitajima, Takafumi; Koizumi, Tsutomu
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no abstracts in English
Miyachi, Shigehiko; Nakahara, Masaumi; Sano, Yuichi; Nomura, Kazunori; Kitajima, Takafumi; Koizumi, Tsutomu
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The hot experiments on solvent extraction conducted in the Chemical Processing Facility (CPF) has demonstrated that the oxidation of Np in the feed solution from Np(V) to Np(VI) by making the acidity higher than conventional condition is effective in the co-recovery of U, Pu and Np so far. Furthermore, it was confirmed that Np was quantitatively recovered with U and Pu by applying of highly acidic scrubbing solution under the conventional condition of the acidity of the feed solution. The main results obtained are presented in this report.
Koizumi, Tsutomu; Kitajima, Takafumi; Nomura, Kazunori; Kitawaki, Shinichi
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Chemical Processing Facility (CPF) is the facility for the hot experiment. This facility has the cells where irradiated fast reactor fuel can be treated and globeboxes and foods where plutonium and uranium can be treated. The demonstration experiments of the conventional PUREX reprocessing process with fast reactor fuel there from 1982. After that, renovation of CPF was carried out until 2002. From then, the development of the advanced aqueous reprocessing process such as dissolution with high HM concentration, crystallization of U, MA separation and direct extraction using supercritical fluid has been carried out. the development of metal electrorefining process has been carried out, too. The outcomes of the development is used as the fundamental data for fact reactor cycle technology development project (FaCT).
Kaji, Naoya; Nakamura, Kazuhito; Nomura, Kazunori; Shibata, Atsuhiro; Yano, Kimihiko; Washiya, Tadahiro; Kitajima, Takafumi; Koizumi, Tsutomu
no journal, ,
For the purpose of obtaining DFs of the short-life FPs by analysis in the hot experiment, fundamental test of crystallization process was carried out using Fast Experimental Reactor "JOYO" irradiated fuel. In this experiment, DFs of nuclides analyzed by analysis except Cs (Such as Ru-106, Ce-144, Pr-144) and Pu were evaluated to be about 100. It was suggested that there is the condition in which Pu-Cs double salt does not be formed, although DF of Cs had been very low in the past experiments because of forming Pu-Cs double salt.
Nomura, Kazunori; Oyama, Koichi; Ouchi, Shinichi; Miyachi, Shigehiko; Kitajima, Takafumi; Koizumi, Tsutomu
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no abstracts in English
Ouchi, Shinichi; Shibata, Atsuhiro; Nomura, Kazunori; Miyachi, Shigehiko; Kitajima, Takafumi; Koizumi, Tsutomu
no journal, ,
no abstracts in English