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Journal Articles

Approach of Okuma Analysis and Research Center

Miyachi, Shigehiko

Enerugi Rebyu, 37(10), p.19 - 20, 2017/09

The JAEA is currently constructing the Okuma Analysis and Research Center near the TEPCO's Fukushima Daiichi Nuclear Power Station site. These are consists of three buildings; Administrative building and hot laboratories; Laboratory-1 and Laboratory-2. Radioactive analysis in hot laboratories will provide the data needed to establish the strategy and methodology for treatment and disposal of radioactive rubbles, and for the removal methods of fuel debris in the reactors.

JAEA Reports

U, Pu and Np co-recovery in the simplified solvent extraction process; The Extraction behavior of Np at the condition of high HNO$$_{3}$$ concentration feed solution and scrubbing solution

Nakahara, Masaumi; Sano, Yuichi; Miyachi, Shigehiko; Koizumi, Tsutomu; Koyama, Tomozo; Aose, Shinichi

JAEA-Research 2006-030, 43 Pages, 2006/06

JAEA-Research-2006-030.pdf:1.93MB

Concerning the advanced aqueous reprocessing system, the simplified solvent extraction process for U, Pu and Np co-recovery has been investigated. We carried out the counter-current experiment, which aimed for Np oxidation and extraction by high [HNO$$_{3}$$] condition. For preventing Np leakage to the raffinate, feed solution and scrubbing solution with high [HNO$$_{3}$$] were used, which would bring high [HNO$$_{3}$$] in the extraction section and efficient Np oxidation and extraction in this section. In addition, high [HNO$$_{3}$$] in the feed solution could help the pre-oxidation of Np to extractable Np(VI). In the steady state, the Np leakage to the raffinate could be kept under about 1%. The stage efficiencies for these elements were estimated by fitting the concentration profiles calculated by MIXSET-X into the experimental results. The stage efficiency of U, Pu and Np were evaluated 100%, 100% and 98.5% in the extraction section and 95%, 90% and 89% in the stripping section respectively.

Journal Articles

Dissolution of irradiated MOX fuel for highly concentrated solution

Sano, Yuichi; Miyachi, Shigehiko; Koizumi, Tsutomu; Koyama, Tomozo

Proceedings of International Conference on Nuclear Energy System for Future Generation and Global Sustainability (GLOBAL 2005) (CD-ROM), 8 Pages, 2005/10

Dissolution behavior of the irradiated MOX fuel was investigated under high Heavy Metal concentration condition for the feed solution of the crystallization process.

Journal Articles

Extraction of Uranium and Plutonium from Irradiated Fuel in Super-DIREX Reprocessing Method

Miura, Sachiko; Kamiya, Masayoshi; Nomura, Kazunori; Miyachi, Shigehiko; Koyama, Tomozo; Ogumo, Shinya*; Shimada, Takashi*

Abstracts P.30, 30 Pages, 2003/00

None

Journal Articles

Renovation of chemical processing facility for development of advanced fast reactor fuel cycle system in JNC

; Miyachi, Shigehiko; ;

Proceedings of 10th International Conference on Nuclear Engineering (ICONE-10), 0 Pages, 2002/00

None

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

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

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

Development of U, Pu and Np co-recovery process from irradiated fast reactor fuel by solvent extraction

Nomura, Kazunori; Nakahara, Masaumi; Sano, Yuichi; Kamiya, Masayoshi; Miyachi, Shigehiko; 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

Oral presentation

Development of efficient dissolution technology for FBR MOX fuel, 4; Behavior of FP in dissolution for a highly concentrated solution

Nomura, Kazunori; Oyama, Koichi; Ouchi, Shinichi; Miyachi, Shigehiko; Washiya, Tadahiro; Koizumi, Tsutomu

no journal, , 

no abstracts in English

12 (Records 1-12 displayed on this page)
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