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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.
Sugikawa, Susumu; Umeda, Miki; Kobayashi, Fuyumi; Nagata, Masanobu*; Dojiri, Shigeru; Amano, Masae*
Proceedings of International Conference on Nuclear Energy System for Future Generation and Global Sustainability (GLOBAL 2005) (CD-ROM), 4 Pages, 2005/10
The mineralization of radioactive contaminated organic wastes by mediated electrochemical oxidation process has some attractive features as alternative to incineration process: The process operates safely at low temperatures and ambient pressures. JAERI has been investigated the process since 1996 and confirmed complete mineralization of this organic solvent. In order to greatly improve current efficiency for the oxidation reaction, further experiments were performed under condition of strong mixing of organic solvent and anolyte with an aide of ultrasonic wave. The current efficiencies for the oxidation reaction by ultrasonic agitation between organic solvent and anolyte were twice to that by mechanical agitation. On the basis of these results, two processes, one for destruction of a small amount of TBP/dodecane and the other for destruction of intermediate compounds following alkaline hydrolysis of a large amount of TBP/dodecane, were proposed.
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).
Kida, Takashi; Sugikawa, Susumu
JAERI-Tech 2004-019, 30 Pages, 2004/03
JAERI-Tech-2004-019.pdf:1.23MB
It is known that hydrazine nitrate used in nuclear fuel reprocessing plants is an unstable substance thermochemically like hydroxylamine nitrate. In order to take the basic data regarding the reaction of hydrazine nitrate with nitric acid, initiation temperatures and heats of this reaction, effect of impurity on initiation temperature and self-accelerating reaction when it holds at constant temperature for a long time were measured by the pressure vessel type reaction calorimeter etc. In this paper, the experimental data and evaluation of the safe handling of hydrazine nitrate in nuclear fuel reprocessing plants are described.
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.
Kida, Takashi; Umeda, Miki; Sugikawa, Susumu
JAERI-Data/Code 2003-001, 29 Pages, 2003/03
JAERI-Data-Code-2003-001.pdf:6.34MB
MOX dissolution using silver-mediated electrochemical method will be employed for the preparation of plutonium nitrate solution in the criticality safety experiments in NUCEF. A simulation code for the MOX dissolution has been developed for the operating support. In this report an outline of the simulation code is proposed and a comparison with the experimental data and a parameter study on the MOX dissolution rate are described.The principle of this code is based on Zundelevich's model for PuO dissolution using Ag
. The influence of nitrous acid on the material balance of Ag and the surface area of MOX powder on the basis of particle size distribution are taken into consideration in this model. A comparison with experimental data was carried out to confirm a validity of this model. It was confirmed that the behavior of MOX dissolution could adequately be simulated using the appropriate MOX dissolution rate constant. The parameters affecting the dissolution rate were studied, it was found that MOX particle size was major governing factor on the dissolution rate.
Suzuki, Yasufumi; Dojiri, Shigeru; Ono, Akio; Maeda, Atsushi; Sugikawa, Susumu
Proceedings of International Conference on Back-End of the Fuel Cycle: From Research to Solutions (GLOBAL 2001) (CD-ROM), 7 Pages, 2001/09
no abstracts in English
Suzuki, Yasufumi; Maeda, Atsushi; Sugikawa, Susumu; Takeshita, Isao
Proceedings of International Conference on Scientific Research on the Back-end of the Fuel Cycle for the 21st Century (ATALANTE 2000) (Internet), 8 Pages, 2000/10
no abstracts in English
bearing waste treatment by electrochemical oxidation techniqueSugikawa, Susumu; Umeda, Miki
Proceedings of 2nd International Conference on Safewaste 2000, Vol.1, p.357 - 364, 2000/00
no abstracts in English
Fujine, Sachio; Murata, Mikio; Abe, Hitoshi; Takada, Junichi; Tsukamoto, Michio; Miyata, Teijiro*; Ida, Masaaki*; Watanabe, Makio; Uchiyama, Gunzo; Asakura, Toshihide; et al.
JAERI-Research 99-056, p.278 - 0, 1999/09
JAERI-Research-99-056.pdf:22.73MB
no abstracts in English
Takeshita, Isao; Ono, Akio; Izawa, Naoki*; Miyoshi, Yoshinori; Maeda, Atsushi; Sugikawa, Susumu; Miyauchi, Masakatsu
Proceedings of 6th International Conference on Nuclear Criticality Safety (ICNC '99), p.1512 - 1576, 1999/09
no abstracts in English
Tsubata, Yasuhiro; Maeda, Atsushi; Ono, Akio; Sugikawa, Susumu; Takayanagi, Masaji; Takeshita, Isao
Proceedings of International Conference on Future Nuclear Systems (GLOBAL '99) (CD-ROM), 7 Pages, 1999/08
no abstracts in English
Umeda, Miki; Sugikawa, Susumu; ;
JAERI-Tech 98-037, 29 Pages, 1998/08
no abstracts in English
Sugikawa, Susumu; ; Takeshita, Isao; ; ; ; P.Bretault*; R.Vialard*; M.Lecomte*
Proc. of 5th Int. Nucl. Conf. on Recycling, Conditioning and Disposal (RECOD '98), 3, p.931 - 938, 1998/00
no abstracts in English
Miyoshi, Yoshinori; ; Tonoike, Kotaro; Izawa, Naoki; Sugikawa, Susumu; Okazaki, Shuji
Nuclear Technology, 118(1), p.69 - 82, 1997/04
Times Cited Count：14 Percentile：71.99(Nuclear Science & Technology)no abstracts in English
Sugikawa, Susumu; ; ; Nakazaki, Masato; Shirahashi, Koichi; ; ; ; Tsuji, Kenichi*; Tachimori, Shoichi; et al.
JAERI-Tech 97-007, 86 Pages, 1997/03
no abstracts in English
Mineo, Hideaki; ; Takeshita, Isao; Nishizawa, Ichio; Sugikawa, Susumu;
Nuclear Technology, 117(3), p.329 - 339, 1997/03
Times Cited Count：1 Percentile：14.34(Nuclear Science & Technology)no abstracts in English
; Sugikawa, Susumu; ; Miyoshi, Yoshinori; Miyauchi, Masakatsu; Izawa, Naoki
JAERI-Tech 96-058, 28 Pages, 1997/01
no abstracts in English
; Sugikawa, Susumu; Miyauchi, Masakatsu; Okazaki, Shuji; Izawa, Naoki
Proceedings of ENS Class 1 Topical Meeting; Research Facilities for the Future of Nuclear Energy, 0, p.322 - 329, 1996/00
no abstracts in English
; ; Sugikawa, Susumu; Izawa, Naoki
JAERI-Tech 95-038, 44 Pages, 1995/07
no abstracts in English
