Effects of ionic strength on the coordination of Eu(III) and Cm(III) to a Gram-negative bacterium, Paracoccus denitrificans

Ozaki, Takuo; Kimura, Takaumi; Onuki, Toshihiko; Francis, A. J.

Radiochimica Acta, 94(9-11), p.715 - 721, 2006/11

https://doi.org/10.1524/ract.2006.94.9-11.715

no abstracts in English

Characterization of Eu(III) adsorbed onto chitin and chitosan by time-resolved laser-induced fluorescence spectroscopy

Ozaki, Takuo; Kimura, Takaumi; Yoshida, Zenko; Francis, A. J.*

Chemistry Letters, 32(7), p.560 - 561, 2003/07

https://doi.org/10.1246/cl.2003.560

no abstracts in English

Eu Mssbauer spectroscopic study on the EuMO(0y1.0)(M=Th, U)

Masaki, Nobuyuki; Otobe, Haruyoshi; Nakamura, Akio; Harada, Daijitsu*; Ito, Kentaro*; Sasaki, Yoshinobu*; Hinatsu, Yukio*

Journal of Nuclear Science and Technology, 39(Suppl.3), p.217 - 220, 2002/11

http://www.tandfonline.com/doi/abs/10.1080/00223131.2002.10875448

no abstracts in English

Pulse radiolysis study on reactions of a hydrated electron with europium(III); Aminopolycarboxylate complexes in aqueous perchlorate media

Nagaishi, Ryuji; Kimura, Takaumi; Yoshida, Yoichi*; Kozawa, Takahiro*; Tagawa, Seiichi*

Journal of Physical Chemistry A, 106(39), p.9036 - 9041, 2002/10

https://doi.org/10.1021/jp0258311

no abstracts in English

A Study on modeling and numerical simulation of extraction in the CMPO-TBP system

; ;

JNC TN8400 2001-022, 60 Pages, 2001/03

JNC-TN8400-2001-022.pdf:1.31MB

A numerical simulation code for the TRUEX (Transuranium Extraction) process was developed. Concentration profiles of americium and europium were calculated for some experiments of the counter current extraction system those were carried out in CPF (Chemical Processing Facility) by using the code. Calculation profiles were in agreement with the experimental results. Operational conditions were also examinted for the americium recovery experiment by the TRUEX process carried out in the Plutonium Fuel Center. It was shown that lowering the concentration of nitric acid in the scrub solution and decreasing the flow rate of solvent and strip solution was effective for improving the performance of the stripping step and reducing the volume of the waste solution. In order to find the optimum conditions for various experiments, this simulation code was modified to calculate the concentration profiles of other metal elements such as zirconium and iron and the effect of oxalic acid on the extraction behavior of the metal elements. The calculated concentration profiles of americium and europium were varied by this modification. In the experiment at CPF, the calculations were carried out to obtain recovery ratio of americium in the product stream with the amount of oxalic acid added to the process. This calculation result showed that it was possible to improve the performance of decontamination of fission products by increasing oxalic acid concentration added to the process. The calculation was also carried out for finding the optimum conditions of oxalic acid concentration added to the europium recovery process.

Analysis of Cm contained in irradiated fuel of experimental fast reactor "JOYO"; Development of the analytical technique and measurement of Cm

Osaka, Masahiko; Koyama, Shinichi; Mitsugashira, Toshiaki; Morozumi, Katsufumi; Namekawa, Takashi

JNC TN9400 2000-058, 49 Pages, 2000/04

JNC-TN9400-2000-058.pdf:1.22MB

The analytical technique for Cm contained in a MOX FUEL was developed and analysis of Cm contained in irradiated fuel of experimental fast reactor "JOYO" was carried out, to contribute to evaluation of transmutation characteristics of MA nuclide in the fast reactor. The procedure of ion-exchange separation of Cm with nitric acid-methanol mixed media essential for the isotopic analysis in irradiated MOX fuel was adopted considering for being rapid and easy. The fundamental test to grasp separation characteristics of this procedure, such as Cm elution position and separation capacity between Cm and Am or Eu, was carried out. ln applying this procedure to the analysis of Cm contained in actual specimen, separation condition was evaluated and optimized, and the procedure consist of impurity removal and Am removal process was devised. This procedure resulted in high recovery rate of Cm and high removal rate of Am and impurity which becomes a problem in sample handling and mass-spectrometry such as Eu and Cs. The Cm separation test from irradiated MOX fuel was carried out using this technique, and Cm isotopic ratio analysis was enabled. The analytical technique for Cm contained in irradiated MOX fuel was established using the procedure of ion-exchange separation with nitric acid-methanol mixed media. The analysis of Cm contained in irradiated MOX fuel of experimental fast reactor "Joyo" was carried out. As a result, it was revealed from measured data that Cm content rate was 1.4 4.0lO atom%, small amount of Cm was generated and Cm isotopic ratio was constant above burn-up 60GWd/t.

Speciation of europium(III) sorbed on a montmorillonite surface in the presence of polycarboxylic acid by laser-induced fluorescence spectroscopy

Takahashi, Yoshio*; Kimura, Takaumi; Kato, Yoshiharu; Minai, Yoshitaka*

Environmental Science & Technology, 33(22), p.4016 - 4021, 1999/00

https://doi.org/10.1021/es990037n

no abstracts in English

Luminescence study on hydration states of lanthanide(III); polyaminopolycarboxylate complexes in aqueous solution

Kimura, Takaumi; Kato, Yoshiharu

Journal of Alloys and Compounds, 275-277, p.806 - 810, 1998/00

https://doi.org/10.1016/S0925-8388(98)00446-0

no abstracts in English

Comparative study on the hydration states of Cm(III) and Eu(III) in solution and in cation exchange resin

Kimura, Takaumi; Kato, Yoshiharu; Takeishi, Hideyo; G.R.Choppin*

Journal of Alloys and Compounds, 271-273, p.719 - 722, 1998/00

https://doi.org/10.1016/S0925-8388(98)00194-7

no abstracts in English

None

Wada, Yukio; *; ; *

PNC TY8607 97-002, 158 Pages, 1997/05

PNC-TY8607-97-002.pdf:3.2MB

no abstracts in English