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Oral presentation

Engineering scale demonstration test of centrifugal contactor system, 4; System performance of solvent washing by salt-free reagent

Takeuchi, Masayuki; Onose, Tsutomu*; Obu, Yuichi*; Arai, Yoichi; Washiya, Tadahiro; Kitajima, Takafumi; Koizumi, Tsutomu

no journal, , 

no abstracts in English

Oral presentation

Engineering scale demonstration test of centrifugal contactor system, 5; Comparison of solvent washing performance between salt-free and alkali reagents by internal reflux type

Takeuchi, Masayuki; Onose, Tsutomu*; Fujisaku, Kazuhiko*; Arai, Yoichi; Washiya, Tadahiro; Kitajima, Takafumi; Koizumi, Tsutomu

no journal, , 

no abstracts in English

Oral presentation

Development of centrifugal contactor with magnetic bearing system, 4; $$gamma$$-ray irradiation test on magnetic bearing system

Arai, Yoichi; Fujisaku, Kazuhiko*; Koizumi, Satoshi*; Takeuchi, Masayuki; Washiya, Tadahiro; Kitajima, Takafumi; Koizumi, Tsutomu

no journal, , 

no abstracts in English

Oral presentation

Renovation of CPF (Chemical Processing Facility) for development of advanced fast reactor fuel cycle system

Aose, Shinichi; Ogasawara, Koji; Nomura, Kazunori; Miyachi, Shigehiko; Ichige, Yoshiaki; Shinozaki, Tadahiro; Ouchi, Shinichi; Kitajima, Takafumi

no journal, , 

no abstracts in English

Oral presentation

Experience of hot cell renovation work in CPF (Chemical Processing Facility)

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

Oral presentation

Fundamental test of crystallization process; Evaluation of U solubility in solution of irradiated fuel

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.

Oral presentation

Dissolution behavior of the irradiated fast reactor fuel powder; Influence of particle size

Hinai, Hiroshi; Tomita, Yutaka; Nomura, Kazunori; Oyama, Koichi; Kitajima, Takafumi; Koizumi, Tsutomu

no journal, , 

no abstracts in English

Oral presentation

Uranium, plutonium and neptunium co-recovery by single cycle extraction process (Neptunium extraction behaviour on high concentration acid condition)

Miyachi, Shigehiko; Nakahara, Masaumi; Sano, Yuichi; Nomura, Kazunori; Kitajima, Takafumi; Koizumi, Tsutomu

no journal, , 

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.

Oral presentation

The Chemical Processing Facility (CPF); The Basic research field for the advanced fuel cycle recycle technology

Koizumi, Tsutomu; Kitajima, Takafumi; Nomura, Kazunori; Kitawaki, Shinichi

no journal, , 

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).

Oral presentation

Fundamental test of crystallization process; Experience on behavior of FPs in crystallization process by using irradiated MOX fuel

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 $$gamma$$ 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 $$gamma$$ 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.

Oral presentation

Development of efficient dissolution technology for FBR MOX fuel, 2; Dissolution experiment of irradiated MOX fuel by using shortly sheared fuel pieces

Nomura, Kazunori; Oyama, Koichi; Ouchi, Shinichi; Miyachi, Shigehiko; Kitajima, Takafumi; Koizumi, Tsutomu

no journal, , 

no abstracts in English

Oral presentation

Experimental study on fuel shearing with irradiated fast reactor fuel at CPF

Ouchi, Shinichi; Shibata, Atsuhiro; Nomura, Kazunori; Miyachi, Shigehiko; Kitajima, Takafumi; Koizumi, Tsutomu

no journal, , 

no abstracts in English

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