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Journal Articles

Separation of Np from U and Pu using a salt-free reductant for Np(VI) by continuous counter-current back-extraction

Ban, Yasutoshi; Asakura, Toshihide; Morita, Yasuji

Proceedings of International Conference on Nuclear Energy System for Future Generation and Global Sustainability (GLOBAL 2005) (CD-ROM), 5 Pages, 2005/10

An idea for controlling Np behavior in the Purex process is that Np(VI) extracted by TBP is selectively reduced to Np(V) by salt-free reagents and separated from U and Pu. Allylhydrazine is expected as a selective Np(VI) reductant from a view point of reduction rates for Np(VI) and Pu(IV). To confirm the applicability of allylhydrazine, a continuous counter-current back-extraction test of Np(VI) has been carried out using a miniature mixer-settler that consists of two steps: U-Pu recovery (3 stages) and Np separation (4 stages). Experimental results show that at least 90% of Np in feed are back-extracted and separated from U and Pu, therefore, it is confirmed that allylhydrazine is expected to be a selective salt-free reductant of Np(VI).

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:5 Percentile:60.32(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

Solvent-washing process using butylamine in fuel reprocessing

Uchiyama, Gunzo; Fujine, Sachio; Maeda, Mitsuru

Nuclear Technology, 120(1), p.41 - 47, 1997/10

 Times Cited Count:1 Percentile:84.71(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Advanced technology of reprocessing for nuclear fuel cycle

Fujine, Sachio

Enerugi Rebyu, 14(2), p.13 - 15, 1994/01

no abstracts in English

Journal Articles

Process study on neptunium separation using salt-free reductive reagent

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

Solvent Extraction 1990, Part A, p.675 - 680, 1992/00

no abstracts in English

Journal Articles

Development of solvent washing process using butylamine in nuclear fuel reprocessing

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

Proc. of Symp. on Solvent Extraction l991, p.243 - 250, 1991/00

no abstracts in English

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