Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Iimure, Takashi*; Hoki, Takehiro*; Hase, Yoshihiro; Nozawa, Shigeki; Narumi, Issey*; Kihara, Makoto*; Ogushi, Kensuke*
JAEA-Review 2013-059, JAEA Takasaki Annual Report 2012, P. 109, 2014/03
Sugikawa, Susumu; Nakazaki, Masato; Kimura, Akihiro; Kida, Takashi*; Kihara, Takehiro*; Akabori, Mitsuo; Minato, Kazuo; Suda, Kazuhiro*; Chikazawa, Takahiro*
Nihon Genshiryoku Gakkai Wabun Rombunshi, 6(4), p.476 - 483, 2007/12
A one-step simple extraction chromatography method using TODGA (
-tetraoctyl-diglycolamide) adsorbent column has been developed to separate the americium from plutonium-solvent extraction raffinate. The raffinate contained Am(
620 mg/
), Np(107 mg/), Ag(2000 mg/), Fe(290 mg/), Cr(38 mg/), Ni(52 mg/) and trace of TBP. Small-scale and scale-up tests for separation of americium and conversion to americium oxide were carried out in NUCEF. Efforts were made to increase yield and purity of americium. The americium was separated with 83-92% yields and 97-98% purities by small-scale tests and 85-95% yields and 98-99% purities by scale-up tests. The yields for conversion of americium nitrate solution to americium oxide were 89-100% by small-scale tests and 85-96 % by scale-up tests. Approximately 1.8 gram americium oxide was recovered from 6 litres of the raffinate and supplied for the research on the high-temperature chemistry of TRU.
Kokusen, Junya; Seki, Masakazu; Abe, Masayuki; Nakazaki, Masato; Kida, Takashi; Umeda, Miki; Kihara, Takehiro; Sugikawa, Susumu
JAERI-Tech 2005-004, 53 Pages, 2005/03
JAERI-Tech-2005-004.pdf:5.92MB
This report presents operating records of dissolution of uranium dioxide and concentration of uranyl nitrate solution and acid removal, which have been performed from 1994 through 2003, for the purpose of feeding 10% and 6% enriched uranyl nitrate solution fuel to Static Experimental Critical Facility(STACY) and Transient Experimental Critical Facility(TRACY) in Nuclear Fuel Safety Engineering Facility(NUCEF).
Umeda, Miki; Nakazaki, Masato; Kida, Takashi; Sato, Kenji; Kato, Tadahito; Kihara, Takehiro; Sugikawa, Susumu
JAERI-Tech 2003-024, 23 Pages, 2003/03
JAERI-Tech-2003-024.pdf:0.98MB
MOX dissolution with silver mediated electrolytic oxidation method is planned for the preparation of plutonium nitrate solution to be used for criticality safety experiments at Nuclear Fuel Cycle Safety Engineering Research Facility (NUCEF). Silver mediated electrolytic oxidation method uses the strong oxidisation ability of Ag(II) ion. This method is thought to be effective for the dissolution of MOX, which is difficult to be dissolved with nitric acid.In this paper, the results of experiments on dissolution with 100 g of MOX are described. It was confirmed by the results that the MOX powder to be used at NUCEF was completely dissolved by silver mediated electrolytic oxidation method and that Pu(VI) ion in the obtained solution was reduced to tetravalent by means of NO
purging.
cell including dissolver off-gas treatmentMineo, Hideaki; Kihara, Takehiro; ; Kimura, Shigeru; ; ; Uchiyama, Gunzo; Hotoku, Shinobu; Watanabe, Makio; ; et al.
JAERI-Conf 99-004, p.498 - 507, 1999/03
no abstracts in English
Mineo, Hideaki; Kihara, Takehiro; ; ; ; Kimura, Shigeru; Uchiyama, Gunzo; Hotoku, Shinobu; ; ; et al.
Proceedings of International Waste Management Symposium '99 (Waste Manegement '99) (CD-ROM), 6 Pages, 1999/03
no abstracts in English
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
Asakura, Toshihide; Uchiyama, Gunzo; Kihara, Takehiro; Hotoku, Shinobu; ; ; ; ; ; Fujine, Sachio; et al.
Proc. of 5th Int. Nucl. Conf. on Recycling, Conditioning and Disposal (RECOD '98), 1, p.746 - 753, 1998/00
no abstracts in English
Kihara, Takehiro; Sakurai, Tsutomu*; ; Fujine, Sachio
Proc. of 5th Int. Nucl. Conf. on Recycling, Conditioning and Disposal (RECOD '98), 1, p.830 - 837, 1998/00
no abstracts in English
Uchiyama, Gunzo; Kihara, Takehiro; Hotoku, Shinobu; Fujine, Sachio; Maeda, Mitsuru
Radiochimica Acta, 81(1), p.29 - 32, 1998/00
no abstracts in English
Sakurai, Tsutomu; ; M.-L.Ye*; Kihara, Takehiro; Fujine, Sachio
Journal of Nuclear Science and Technology, 34(2), p.211 - 216, 1997/02
Times Cited Count：16 Percentile：75.39(Nuclear Science & Technology)no abstracts in English
Kihara, Takehiro; ; ; ; ; Fujine, Sachio
JAERI-Research 96-070, 23 Pages, 1997/01
JAERI-Research-96-070.pdf:1.0MB
no abstracts in English
Kihara, Takehiro; Fujine, Sachio; ; ; Maeda, Mitsuru;
Journal of Nuclear Science and Technology, 33(5), p.409 - 413, 1996/05
Times Cited Count：2 Percentile：24.61(Nuclear Science & Technology)no abstracts in English
Kihara, Takehiro; S.I.Sinkov*; Fujine, Sachio; Maeda, Mitsuru
Value Adding Through Solvent Extraction (Proc. of ISEC 96), 2, p.1603 - 1607, 1996/00
no abstracts in English
S.I.Sinkov*; Kihara, Takehiro; Fujine, Sachio; Maeda, Mitsuru
JAERI-Tech 95-016, 48 Pages, 1995/03
no abstracts in English
Kihara, Takehiro; ; Fujine, Sachio; Maeda, Mitsuru; ;
JAERI-M 93-234, 47 Pages, 1993/12
no abstracts in English
Hotoku, Shinobu; Kihara, Takehiro; Uchiyama, Gunzo; Fujine, Sachio; Maeda, Mitsuru
JAERI-M 93-095, 19 Pages, 1993/03
no abstracts in English
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
Kihara, Takehiro; Fujine, Sachio; ; ; Maeda, Mitsuru;
Solvent Extraction 1990, Part A, p.497 - 502, 1992/00
no abstracts in English
Uchiyama, Gunzo; Hotoku, Shinobu; Kihara, Takehiro; Fujine, Sachio; Maeda, Mitsuru
Solvent Extraction 1990, Part A, p.675 - 680, 1992/00
no abstracts in English
