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Journal Articles

Technetium separation for future reprocessing

Asakura, Toshihide; Hotoku, Shinobu; Ban, Yasutoshi; Matsumura, Masakazu; Morita, Yasuji

Journal of Nuclear and Radiochemical Sciences, 6(3), p.271 - 274, 2005/12

Tc extraction and separation experiments were performed basing on PUREX technique with using spent UO$$_{2}$$ fuel with burn-up of 44 GWd/t. The experimental results were examined with performing calculations by a simulation code ESSCAR (Extraction System Simulation Code for Advanced Reprocessing). It was demonstrated that Tc can be almost quantitatively extracted from a dissolver solution and that Tc can also be almost quantitatively recovered by scrubbing. Further, it was clearly presented from the calculation results of ESSCAR that the extraction mechanism of Tc is dominated by the synergistic effect of Zr and U.

Journal Articles

Reprocessing technologies of the High Temperature Gas-cooled Reactor (HTGR) fuel

Sumita, Junya; Ueta, Shohei; Kunitomi, Kazuhiko; Yoshimuta, Shigeharu*; Sawa, Kazuhiro

Nihon Genshiryoku Gakkai Wabun Rombunshi, 2(4), p.546 - 554, 2003/12

A High Temperature Gas-Cooled Reactor (HTGR) is particularly attractive due to capability of producing high temperature helium gas and its inherent safety characteristic. Research and development of high temperature gas turbine plant and high temperature heat utilizing technology are now undergoing. The High Temperature Engineering Test Reactor (HTTR) is a research facility constructed by the Japan Atomic Energy Research Institute. This paper describes reprocessing technology of HTGR fuels. Coated fuel particles, consisted of a microsphere of low enriched UO$$_{2}$$ with TRISO particles, are used as the HTGR fuels. In order to reprocess HTGR fuels, a head-end process is needed and JAERI had confirmed jet-grind method as basic technologies of the head-end process. Since Purex method can be used after the head-end process, a reprocessing system for the HTGR fuels could be established. Also the preliminary study on the methodology for disposing graphite blocks in a HTGR was carried out, and its evaluation results were briefly presented.

Journal Articles

Extraction behavior of TRU elements in the nuclear fuel reprocessing

Hotoku, Shinobu; Asakura, Toshihide; Mineo, Hideaki; Uchiyama, Gunzo

Journal of Nuclear Science and Technology, 39(Suppl.3), p.313 - 316, 2002/11

no abstracts in English

Journal Articles

Long-lived nuclide separation for advancing back-end fuel cycle process

Uchiyama, Gunzo; Mineo, Hideaki; Asakura, Toshihide; Hotoku, Shinobu; Iizuka, Masaru*; Fujisaki, Susumu; Isogai, Hikaru; Ito, Yoshinori*; Sato, Makoto; Hosoya, Noriaki

Journal of Nuclear Science and Technology, 39(Suppl.3), p.925 - 928, 2002/11

no abstracts in English

Journal Articles

Development of an advanced reprocessing process of spent nuclear fuel

Uchiyama, Gunzo; Mineo, Hideaki; Asakura, Toshihide; Hotoku, Shinobu

Nihon Kikai Gakkai Dai-8-Kai Doryoku, Enerugi Gijutsu Shimpojiumu Koen Rombunshu, p.483 - 488, 2002/00

no abstracts in English

Journal Articles

Advanced technologies for long-lived nuclides separation in reprocessing

Uchiyama, Gunzo; Mineo, Hideaki; Asakura, Toshihide; Hotoku, Shinobu

Proceedings of International Conference on Back-End of the Fuel Cycle: From Research to Solutions (GLOBAL 2001) (CD-ROM), 8 Pages, 2001/09

no abstracts in English

Journal Articles

PARC process for an advanced PUREX process

Uchiyama, Gunzo; Mineo, Hideaki; Hotoku, Shinobu; Asakura, Toshihide; Kamei, Kazushige; Watanabe, Makio; Nakano, Yuji*; Kimura, Shigeru; Fujine, Sachio

Progress in Nuclear Energy, 37(1-4), p.151 - 156, 2000/12

 Times Cited Count:7 Percentile:48.29(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Management of minor long-lived nuclides in nuclear fuel reprocessing

Uchiyama, Gunzo; Mineo, Hideaki; Asakura, Toshihide; Hotoku, Shinobu; Kamei, Kazushige; Watanabe, Makio; Fujine, Sachio

Proceedings of 12th Pacific Basin Nuclear Conference (PBNC 2000), Vol.1, p.531 - 538, 2000/00

no abstracts in English

Journal Articles

Reduction of minor nuclides in nuclear fuel reprocessing

Uchiyama, Gunzo; Mineo, Hideaki; Asakura, Toshihide; Hotoku, Shinobu; Kamei, Kazushige; Watanabe, Makio; Fujine, Sachio

Proceedings of 2nd International Conference on Safewaste 2000, Vol.2, p.689 - 700, 2000/00

no abstracts in English

Journal Articles

Development of treatment technology for carbon-14 in dissolver off-gas of spent fuel

Mineo, Hideaki; ; *; Uchiyama, Gunzo; Fujine, Sachio

Proc. of 7th Int. Conf. on Radioactive Waste Mamagement and Environmental Remediation (ICEM '99)(CD-ROM), 3 Pages, 1999/00

no abstracts in English

Journal Articles

Spent fuel test of an advanced PUREX process:PARC

Mineo, Hideaki; Uchiyama, Gunzo; Hotoku, Shinobu; Asakura, Toshihide; Kihara, Takehiro; *; ; Kimura, Shigeru; *; ; et al.

Proc. of Int. Conf. on Future Nuclear Systems (GLOBAL'99)(CD-ROM), 7 Pages, 1999/00

no abstracts in English

Journal Articles

Management of neptunium and technetium in an advanced PUREX process

Uchiyama, Gunzo; Hotoku, Shinobu; Watanabe, Makio; Kamei, Kazushige; Mineo, Hideaki; Nakano, Yuji*; Kimura, Shigeru; Asakura, Toshihide; Fujine, Sachio

Proceedings of 7th International Conference on Radioactive Waste Management and Environmental Remediation (ICEM '99) (CD-ROM), p.5 - 0, 1999/00

no abstracts in English

Journal Articles

Reduction of neptunium (VI) by butyraldehyde isomers in nitric acid solution

Uchiyama, Gunzo; Hotoku, Shinobu; Fujine, Sachio; Maeda, Mitsuru

Nuclear Technology, 122(2), p.222 - 227, 1998/05

 Times Cited Count:14 Percentile:74.48(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

A Model on valence state evaluation of TRU nuclides in reprocessing solutions

Uchiyama, Gunzo; Fujine, Sachio; Yoshida, Zenko; Maeda, Mitsuru; *

JAERI-Research 98-005, 20 Pages, 1998/02

JAERI-Research-98-005.pdf:0.63MB

no abstracts in English

Journal Articles

Destruction of butyraldehyde isomers using silver catalyzed electrochemical oxidation

Uchiyama, Gunzo; Fujine, Sachio

Journal of Radioanalytical and Nuclear Chemistry, 230(1-2), p.105 - 109, 1998/00

 Times Cited Count:3 Percentile:32.94(Chemistry, Analytical)

no abstracts in English

Journal Articles

Extraction behaviors of uranium, plutonium, neptunium and technetium in PARC process

Uchiyama, Gunzo; Asakura, Toshihide; Hotoku, Shinobu; Fujine, Sachio

Proc. of 5th Int. Nucl. Conf. on Recycling, Conditioning and Disposal (RECOD '98), 1, p.393 - 400, 1998/00

no abstracts in English

Journal Articles

Development of a new neptunium separation process by using photochemical reduction in nuclear fuel reprocessing

Uchiyama, Gunzo; Kihara, Takehiro; Hotoku, Shinobu; Fujine, Sachio; Maeda, Mitsuru

Radiochimica Acta, 81(1), p.29 - 32, 1998/00

no abstracts in English

Journal Articles

The Separation of neptunium and technetium in an advanced Purex process

Uchiyama, Gunzo; Asakura, Toshihide; Hotoku, Shinobu; Fujine, Sachio

Solvent Extr. Ion Exch., 16(5), p.1191 - 1213, 1998/00

no abstracts in English

Journal Articles

Distribution of nitrous acid between tri-n-butyl phosphate/n-dodecane and nitric acid

Uchiyama, Gunzo; Hotoku, Shinobu; Fujine, Sachio

Solvent Extr. Ion Exch., 16(5), p.1177 - 1190, 1998/00

 Times Cited Count:9 Percentile:48.93(Chemistry, Multidisciplinary)

no abstracts in English

Journal Articles

The Separation of neptunium and technetium in an advanced purex process

Uchiyama, Gunzo; Asakura, Toshihide; Hotoku, Shinobu; Fujine, Sachio

Solvent Extr. Ion Exch., 16(5), p.1191 - 1213, 1998/00

 Times Cited Count:11 Percentile:53.18(Chemistry, Multidisciplinary)

no abstracts in English

36 (Records 1-20 displayed on this page)