NiO/NbO/C hydrazine electrooxidation catalysts for anion exchange membrane fuel cells

Sakamoto, Tomokazu*; Masuda, Teruyuki*; Yoshimoto, Koji*; Kishi, Hirofumi*; Yamaguchi, Susumu*; Matsumura, Daiju; Tamura, Kazuhisa; Hori, Akihiro*; Horiuchi, Yosuke*; Serov, A.*; et al.

Journal of the Electrochemical Society, 164(4), p.F229 - F234, 2017/01

https://doi.org/10.1149/2.0281704jes

Operando XAFS study of carbon supported Ni, NiZn, and Co catalysts for hydrazine electrooxidation for use in anion exchange membrane fuel cells

Sakamoto, Tomokazu*; Matsumura, Daiju; Asazawa, Koichiro*; Martinez, U.*; Serov, A.*; Artyushkova, K.*; Atanassov, P.*; Tamura, Kazuhisa; Nishihata, Yasuo; Tanaka, Hirohisa*

Electrochimica Acta, 163, p.116 - 122, 2015/05

https://doi.org/10.1016/j.electacta.2015.02.156

Back-extraction of tri- and tetravalent actinides from Di(2-ethylhexyl)phosphoric acid (HDEHP) with hydrozine carbonate

Watanabe, Masayuki; Morita, Yasuji; Kubota, Masumitsu*; Tatsugae, Ryozo*

Radiochimica Acta, 87(3-4), p.115 - 119, 1999/00

https://doi.org/10.1524/ract.1999.87.34.115

no abstracts in English

None

PNC TJ1609 96-001, 36 Pages, 1996/02

PNC-TJ1609-96-001.pdf:0.89MB

no abstracts in English

Kinetics of reduction of uranium(VI) to uranium(IV) at titanium electrode in nitric acid and hydrazine media

K-W.Kim*; J-D.Kim*; Aoyagi, Hisao; Yoshida, Zenko

Journal of Nuclear Science and Technology, 31(4), p.329 - 334, 1994/04

https://doi.org/10.3327/jnst.31.329

no abstracts in English

Pretreatment of a titanium electrode for reduction of Uranium(VI) in nitric acid-hydrazine media

K.-W.Kim*; J.-D.Kim*; Aoyagi, Hisao; ; Yoshida, Zenko

Journal of Nuclear Science and Technology, 30(6), p.554 - 559, 1993/06

https://doi.org/10.3327/jnst.30.554

no abstracts in English

Studies on the partitioning of high level liquid waste; Extraction of transuranium and fission products with DBBP, TBP, D2EHPA and D/M2EHPA (mixed solvent)

Kishimoto, Yoichiro; Kawata, Tomio*; *

PNC TN8410 87-08, 125 Pages, 1987/05

PNC-TN8410-87-08.pdf:2.04MB

This paper is to present the technology developed in WTL, PNC for the partitioning of actinides in High Level Liquid Waste (HLLW) from nuclear fuel reprocessing plant. Partitioning experiments were primarily made with the batch extraction method, and the counter current continuous extraction method was also examined by using a laboratory scale mixer-settler. Extractants used were Dibutylbutyl Phosphonate (DBBP), Tri-n-butyl Phosphate (TBP), Di (2-ethylhexyl) Phosphoric Acid (D2EHPA) and Di-Mono (2-ethylhexyl) Phosporic Acid mixture (D/M2EHPA, mol ratio D/M=1/1). Other studies were made of the reduction of Pu (IV) or Fe (III) by hydrazine in the nitric acid solution with the active charcoal catalyst. Further studies were also made of the effect of the lactic acid addition on the extraction of Pu (IV) and U (VI) by TBP. The results from the batch extraction of Am (III), Eu(III), and Ce(III) in the DBBP, TBP, D2EHPA or D/M2EHPA-HNO-M (NO) systems showed the linear relationship between log (E/ORG) vs. log (NO) aq and log E vs. log (H)aq. The apparent equilibrium constants (Km) of 1.10 (Am-DBBP), 1.26 (Eu-DBBP), 1.22(Ce-DBBP), 0.0352(Am-TBP), 0.0549(Eu-TBP), 0.0312(Ce-TBP), 0.845(Am-D2EHPA), 22(Am-D/M2EHPA), 22.7(Eu-D/M2EHPA) and 18.7(Ce-D/M2EHPA) were obtained from there relationships. For the reduction of Pu (IV) and Fe (III) in the HNO-hydrazine-active chacoal catalyst system, a good linearity between the reaction ratio and the reduction time was observed, and the reaction was apparently of the first order. The reduction rates of Pu (IV) and Fe (III) in this system were significantly increased by 300 times that observed in the system without the active chacoal catalyst. The addition of lactic acid to the system of HNO-U-Pu-TBP lowered the extractability of Pu (IV) to TBP, and the distribution coefficient of Pu (IV), for example, was in the vicinity of that for Pu (III) in the 0.5N HNO-0.3M lactic acid soluti

Effect of hydrazine injection into spent fuel pools in the Fukushima Daiichi Nuclear Power Station and issues relating to the long-term reliability of fuel assemblies

Motooka, Takafumi

no journal, , 

The subjects "Effect of hydrazine injection on spent fuel pools in the Fukushima Daiichi Nuclear Power Station and issues relating to the long-term reliability of fuel assemblies" are discussed. The effect of -ray irradiation on deoxydation in aqueous solution by hydrazine was investigated using pure water and artificial sea water at room temperature. Concentration of dissolved oxygen was not decreased without -ray irradiation, while concentration of dissolved oxygen was markedly decreased for one hour -ray irradiation. It is believed that the small hydrazine addition to spent nuclear fuel pool water is effective as a method for decreasing concentration of dissolved oxygen.