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Journal Articles

Study on coordination structure of Re adsorbed on Mg-Al layered double hydroxide using X-ray absorption fine structure

Tanaka, Kazuya; Kozai, Naofumi; Onuki, Toshihiko; Grambow, B.

Journal of Porous Materials, 26(2), p.505 - 511, 2019/04

https://doi.org/10.1007/s10934-018-0634-z

Times Cited Count：4 Percentile：42.73(Chemistry, Applied)

In this study, we utilized X-ray absorption fine structure spectroscopy to clarify the coordination structure of Re in Mg-Al LDH as a surrogate of Tc. Adsorption experiments of ReO $_{4}$ $^{-}$ on calcined and uncalcined Mg-Al LDHs were conducted in aqueous solutions with different concentrations of NaCl, NaNO $_{3}$ , and Na $_{2}$ SO $_{4}$ . Calcined Mg-Al LDH showed much higher adsorption than uncalcined one. The adsorption of ReO $_{4}$ $^{-}$ was reversible, and decreased with increasing concentration of competing anions like Cl $^{-}$ , NO $_{3}$ $^{-}$ , or SO $_{4}$ $^{2-}$ . Analysis of Re L $_{III}$ -edge extended X-ray absorption fine structure indicated that ReO $_{4}$ $^{-}$ was adsorbed as an outer-sphere complex on Mg-Al LDH. The observed Re adsorption-desorption behavior, which was sensitive to the presence of competing anions, was consistent with the formation of outer sphere-complex.

Journal Articles

Rapid separation of zirconium using microvolume anion-exchange cartridge for $^{93}$ Zr determination with isotope dilution ICP-MS

Asai, Shiho; Hanzawa, Yukiko; Konda, Miki; Suzuki, Daisuke; Magara, Masaaki; Kimura, Takaumi; Ishihara, Ryo*; Saito, Kyoichi*; Yamada, Shinsuke*; Hirota, Hideyuki*

Talanta, 185, p.98 - 105, 2018/08

https://doi.org/10.1016/j.talanta.2018.03.026

Times Cited Count：7 Percentile：55.46(Chemistry, Analytical)

Estimating the risks associated with radiation from long-lived fission products (LLFP) in radioactive waste is essential to ensure the long-term safety of potential disposal sites. In this study, the amount of $^{93}$ Zr, a LLFP, was determined by ICP-MS after separating Zr from a spent nuclear fuel solution using a microvolume anion-exchange cartridge (TEDA cartridge). The TEDA cartridge achieved highly selective separation of Zr regardless of its small bed volume of 0.08 cm $^{3}$ . The time taken to complete the Zr separation was 1.2 min with a flow rate of 1.5 mL/min, which was 10 times faster than that for a conventional anion-exchange resin column. Almost all the other elements were removed, leading to accurate measurement of $^{93}$ Zr. The result connects experimental value to theoretical prediction provided by ORIGEN2, which requires verification. With the measured value, we demonstrated that the theoretical value is reliable enough to estimate radiation risks.

Journal Articles

Anion-exchange separation of americium and the lanthanides using a single column

Miyamoto, Yutaka; Yasuda, Kenichiro

Journal of Nuclear and Radiochemical Sciences (Internet), 18, p.13 - 15, 2018/07

http://www.radiochem.org/en/paper/JN181/jn18104.pdf

A sequential separation technique using an anion-exchange column developed in the previous works have the potential to completely separate picograms of Am from the lanthanides using mixtures of acetic acid, hydrochloric acid, and nitric acid as the eluents, without any functional ligands or special columns. This experimental result implies that ultra-trace actinides, including Am, Pu, U, and Th in environmental samples can be sequentially separated by combination of these mixed-media eluents and an anion exchange column.

Journal Articles

Extraction of europium(III) into W/O microemulsion containing aerosol OT and a bulky diamide, 1; Cooperative effect

Suzuki, Hideya*; Naganawa, Hirochika; Tachimori, Shoichi

Solvent Extraction and Ion Exchange, 21(4), p.527 - 546, 2003/03

https://doi.org/10.1081/SEI-120022519

Times Cited Count：11 Percentile：55.23(Chemistry, Multidisciplinary)

no abstracts in English

Journal Articles

Speciation of Eu(III) in an anion exchange separation system with LiCl-H $_{2}$ O/alcohol mixed media by time-resolved laser-induced fluorescence spectroscopy

Arisaka, Makoto*; Kimura, Takaumi; Suganuma, Hideo*; Yoshida, Zenko

Journal of Radioanalytical and Nuclear Chemistry, 255(2), p.385 - 389, 2003/02

https://doi.org/10.1023/A:1022529525952

Times Cited Count：5 Percentile：61.28(Chemistry, Analytical)

no abstracts in English

Journal Articles

Direct evidence for enchanced inner-sphere chloro complexation of Eu(III) and Cm(III) in anion exchange resin phase studies by time-resolved laser-induced fluorescence spectroscopy

Arisaka, Makoto*; Kimura, Takaumi; Suganuma, Hideo*; Yoshida, Zenko

Radiochimica Acta, 90(4), p.193 - 197, 2002/05

https://doi.org/10.1524/ract.2002.90.4_2002.193

Times Cited Count：12 Percentile：36.27(Chemistry, Inorganic & Nuclear)

no abstracts in English

Journal Articles

The Effect of hydrophobic picrate on the extraction and separation of lanthanides(III) with carbamoylmethylene phosphine oxide

Naganawa, Hirochika; Suzuki, Hideya; Tachimori, Shoichi; Nasu, Akinobu*; Sekine, Tatsuya*

Physical Chemistry Chemical Physics, 3(12), p.2509 - 2517, 2001/06

https://doi.org/10.1039/b100073j

Times Cited Count：29 Percentile：31.08(Chemistry, Physical)

no abstracts in English

JAEA Reports

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 $^{-3}$ atom%, small amount of $^{247}$ Cm was generated and Cm isotopic ratio was constant above burn-up 60GWd/t.

Journal Articles

Determination of thorium and uranium in activated concrete by inductively coupled plasma mass spectrometry after anion-exchange separation

Kato, Kaneharu; Ito, Mitsuo; Watanabe, Kazuo

Fresenius Journal of Analytical Chemistry, 366(1), p.55 - 58, 2000/01

no abstracts in English

JAEA Reports

None

PNC-TJ6614 93-001, 32 Pages, 1993/03

PNC-TJ6614-93-001.pdf:0.61MB

None

JAEA Reports

A Radioanalytical Method for Samarium-151 and Promethium-147in Environmental Samples

Sumiya, Shuichi; Hayashi, Naomi; ; Narita, Osamu

PNC-TN8430 91-001, 45 Pages, 1990/12

PNC-TN8430-91-001.pdf:0.85MB

A radioanalytical method for low level samarium-151(Sm-151) and promethium-147(Pm-147) in environmental samples has been studied for the environmental assessment around nuclear facilities. In this study, we use the separation method with high performance liquid chromatography (HPLC) to determine Sm-151 and Pm-147 in environmental samples such as sea sediments and marine organisms. Samarium-151 and Pm-147 in environmental samples are coprecipitated with other lanthanoids after adding neodymium(Nd). These nuclides are purified by anion exchange methods in methanol-mineral acid media. After the purification, Sm-151 and Pm-147 are separated with HPLC in lactic acid-sodium hydroxide media, and determined with liquid scintillation counting, respectively. The Nd is determined by inductively coupled plasma atomic emission spectrometry (ICP-AES) to correct chemical recoveries of these nuclides. The detection limits for Sm-151 and Pm-147 in this method are about 0.01Bq/sample.

Journal Articles