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Journal Articles

Determination of the carbon ion beam irradiation condition for barley

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

Journal Articles

Separation of americium from plutonium-solvent extraction raffinate and conversion to americium oxide

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 (${it N,N,N,N'}$-tetraoctyl-diglycolamide) adsorbent column has been developed to separate the americium from plutonium-solvent extraction raffinate. The raffinate contained Am($$sim$$620 mg/$$l$$), Np($$sim$$107 mg/$$l$$), Ag($$sim$$2000 mg/$$l$$), Fe($$sim$$290 mg/$$l$$), Cr($$sim$$38 mg/$$l$$), Ni($$sim$$52 mg/$$l$$) 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.

JAEA Reports

Report on the fuel treatment facility operation

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).

JAEA Reports

Characteristics of MOX dissolution with silver mediated electrolytic oxidation method

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$$_{2}$$ purging.

Journal Articles

Dissolution tests of spent fuel in the NUCEF $$alpha$$$$gamma$$ cell including dissolver off-gas treatment

Mineo, 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

Journal Articles

Study on gaseous effluent treatment during dissolusion tests of spent fuel

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

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

Iodine behavior during dissolution process within NUCEF-BECKY

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

Journal Articles

A Test line newly installed in NUCEF and research program on advanced reprocessing process by utilizing it

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

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

Trapping and measuring radioiodine (iodine-129) in cartridge filters

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:13 Percentile:71.61(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Study on dissolution method of residue and analytical method of dissolver solution of dissolution process in NUCEF-Becky

Kihara, Takehiro; *; ; *; *; Fujine, Sachio

JAERI-Research 96-070, 23 Pages, 1997/01

JAERI-Research-96-070.pdf:1.0MB

no abstracts in English

Journal Articles

Laser induced photoacoustic spectroscopy for analysis of neptunium(V) ions under PUREX process condition

Kihara, Takehiro; Fujine, Sachio; *; *; Maeda, Mitsuru; *

Journal of Nuclear Science and Technology, 33(5), p.409 - 413, 1996/05

 Times Cited Count:2 Percentile:25.51(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Application of optical fiber system for photoacoustic spectroscopy

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

JAEA Reports

Study on the photoacoustic spectroscopy capabilities with remote detection for monitoring of actinide species in nuclear fuel reprocessing solutions

S.I.Sinkov*; Kihara, Takehiro; Fujine, Sachio; Maeda, Mitsuru

JAERI-Tech 95-016, 48 Pages, 1995/03

JAERI-Tech-95-016.pdf:1.7MB

no abstracts in English

JAEA Reports

Development of sensitive analytical technique by laser-induced photoacoustic spectroscopy

Kihara, Takehiro; *; Fujine, Sachio; Maeda, Mitsuru; *; *

JAERI-M 93-234, 47 Pages, 1993/12

JAERI-M-93-234.pdf:1.7MB

no abstracts in English

JAEA Reports

Distribution equilibrium of nitrous acid in reprocessing solution

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

JAERI-M 93-095, 19 Pages, 1993/03

JAERI-M-93-095.pdf:0.66MB

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

Journal Articles

Application of laser induced photoacoustic spectroscopy system to the determination of transuranic elements

Kihara, Takehiro; Fujine, Sachio; *; *; Maeda, Mitsuru; *

Solvent Extraction 1990, Part A, p.497 - 502, 1992/00

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

22 (Records 1-20 displayed on this page)