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Journal Articles

Study on the mechanism of radiolytic degradation of an extractant for minor actinides separation

Toigawa, Tomohiro; Murayama, Rin*; Kumagai, Yuta; Yamashita, Shinichi*; Suzuki, Hideya; Ban, Yasutoshi; Matsumura, Tatsuro

UTNL-R-0501, p.24 - 25, 2020/12

This report summarizes the results obtained in FY2019 at Electron Linac Facility of University of Tokyo. The radiolysis process of a diglycolamide extractant, which is expected to be used in the separation process of minor actinides (MA), in dodecane and octanol solutions was investigated by pulse radiolysis. As a result, it was suggested that by adding alcohol, the decomposition process of the diglycolamide extractant was different from the decomposition processes in the single solvent of dodecane considered that the decomposition occurred via a radical cation species of the extractant.

Journal Articles

Application of turbidity measurement for evaluation of two-phase separation in ${it N}$,${it N}$-dialkylamides-nitric acid systems

Tsutsui, Nao; Ban, Yasutoshi; Hakamatsuka, Yasuyuki; Urabe, Shunichi; Matsumura, Tatsuro

Proceedings of 21st International Conference & Exhibition; Nuclear Fuel Cycle for a Low-Carbon Future (GLOBAL 2015) (USB Flash Drive), p.1153 - 1157, 2015/09

${it N}$,${it N}$-Dialkylamides are promising alternative extractants to tri-${it n}$-butyl phosphate in the reprocessing of spent nuclear fuels, but the two-phase separation between their organic and aqueous phases has not been evaluated quantitatively. ${it N}$,${it N}$-Di(2-ethylhexyl)-2,2-dimethylpropanamide (DEHDMPA) in ${it n}$-dodecane were agitated with uranyl nitrate-containing nitric acid, and their turbidities and their uranium distribution ratios were measured with respect to the time for the quantitative evaluation. Increasing DEHDMPA, uranium, and nitric acid concentrations enhanced turbidities. Although turbidities decreased with respect to the time, uranium distribution ratios slightly changed, indicating the observed turbidities did not affect these uranium distribution ratios significantly. Therefore, DEHDMPA may act as suitable extractant for uranium in nitric acid from two-phase separation viewpoint, and turbidity may be an indicator for extractant performance evaluation.

JAEA Reports

Proceedings of the International symposium NUCEF 2005; February 9-10, 2005, Techno Community Square RICOTTI, Tokai-mura, Ibaraki-ken, Japan

International Symposium NUCEF 2005 Working Group

JAERI-Conf 2005-007, 359 Pages, 2005/08

JAERI-Conf-2005-007.pdf:24.79MB

Japan Atomic Energy Research Institute (JAERI) held the international symposium NUCEF2005 at Techno Community Square RICOTTI in Tokai-mura on February 9 and 10, 2005. This symposium was co-organized by Japan Nuclear Cycle Development Institute (JNC), and Nuclear Fuel Cycle Safety Research Committee authorized the program. Two hundred thirty-nine participants from 11 countries presented fifty-nine papers, and discussed recent research activities and its outputs on waste disposal safety, fuel cycle facility safety including criticality safety, and separation process development. The presented papers are compiled in the proceedings.

Journal Articles

Simulation codes of chemical separation process of spent fuel reprocessing; Tool for process development and safety research

Asakura, Toshihide; Sato, Makoto; Matsumura, Masakazu; Morita, Yasuji

JAERI-Conf 2005-007, p.345 - 347, 2005/08

This paper reviews the succeeding development and utilization of Extraction System Simulation Code for Advanced Reprocessing (ESSCAR). From the viewpoint of development, more tests with spent fuel and calculations should be performed with better understanding of the physico-chemical phenomena in a separation process. From the viewpoint of process safety research on fuel cycle facilities, it is important to know the process behavior of a key substance; being highly reactive but existing only trace amount.

Journal Articles

Research on PARC process for future reprocessing

Asakura, Toshihide; Hotoku, Shinobu; Ban, Yasutoshi; Matsumura, Masakazu*; Kim, S.-Y.; Mineo, Hideaki; Morita, Yasuji

Proceedings of International Conference ATALANTE 2004 Advances for Future Nuclear Fuel Cycles, 5 Pages, 2004/06

In JAERI, PARC process based on PUREX technique has been studied to as the basis of future reprocessing. The key of concept is to obtain the products, U and Pu, within only a single extraction cycle by separating Np and Tc from U and Pu before U/Pu partition. Two flow-sheet tests on the process were performed with 44 GWd/t PWR spent-fuel solutions. It was demonstrated that remaining Np in raffinate from co-extraction could be decreased to 13 % compared to the dissolver solution with increased solvent flow rate and with increased nitric acid concentration of FP scrubbing solution. It was demonstrated that Np separation (selective reduction by n-butyraldehyde) efficiency could be improved from 36 % to 78 % by flow-sheet modification; increasing reductant concentration and scrubbing solution flow rate. The feasibility of the Tc separation technique by high acid scrubbing was demonstrated.

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

JAEA Reports

Proceedings of the International Symposium NUCEF 2001; Scientific Bases for Criticality Safety, Separation Process and Waste Disposal

NUCEF 2001 Symposium Working Group

JAERI-Conf 2002-004, 714 Pages, 2002/03

JAERI-Conf-2002-004.pdf:69.13MB

This volume contains 94 papers presented at the 3rd NUCEF International Symposium NUCEF 2001 held on October 31 - November 2, 2001, in Tokai, Japan, following the 1st symposium NUCEF'95 (Proceedings: JAERI-Conf 96-003) and the 2nd symposium NUCEF'98 (Proceedings: JAERI-Conf 99-004). The theme of this symposium was " Scientific Basis for Criticality Safety, Separation Process and Waste Disposal". The papers were presented in oral and poster sessions on following research fields: (1) Separation Process, (2) TRU Chemistry, (3) Radioactive Waste Disposal, (4) Criticality Safety.

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 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

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

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

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

Journal Articles

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

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

Solvent Extr. Ion Exch., 15(5), p.863 - 877, 1997/00

 Times Cited Count:2 Percentile:19.85(Chemistry, Multidisciplinary)

no abstracts in English

JAEA Reports

IS Process for thermochemical hydrogen production

Onuki, Kaoru; Nakajima, Hayato; Ioka, Ikuo; Futakawa, Masatoshi; Shimizu, Saburo

JAERI-Review 94-006, 53 Pages, 1994/11

JAERI-Review-94-006.pdf:1.52MB

no abstracts in English

JAEA Reports

Separation of neptunium, plutonium and uranium by using butyraldehydes as reductants in reprocessing

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

JAERI-M 93-198, 27 Pages, 1993/10

JAERI-M-93-198.pdf:0.92MB

no abstracts in English

Journal Articles

New separation process for neptunium plutonium, and uranium using butyraldehydes as reductants in reprocessing

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

Nuclear Technology, 102, p.341 - 352, 1993/06

 Times Cited Count:40 Percentile:94.74(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Study on the selective reduction of neptunium(VI) by an electrochemical method in the Purex process

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

Solvent Extraction in the Process Industries, Vol. 3, p.1797 - 1804, 1993/00

no abstracts in English

25 (Records 1-20 displayed on this page)