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Journal Articles

Quantitative imaging of trace elements in solid samples by online isotope dilution laser ablation-inductively coupled plasma-mass spectrometry

Yanagisawa, Kayo; Matsueda, Makoto; Furukawa, Makoto*; Ishiniwa, Hiroko*; Wada, Toshihiro*; Hirata, Takafumi*; Takagai, Yoshitaka*

Analyst, 148(18), p.4291 - 4299, 2023/09

 Times Cited Count:0 Percentile:0(Chemistry, Analytical)

Quantitative imaging of trace elements was successfully performed by online isotope dilution laser ablation inductively coupled plasma mass spectrometry (online LA-ICP-IDMS). The sample aerosols produced by LA are mixed online with the mist created from an isotopically enriched spike solution via an in-house cyclonic spray chamber, which has a gas port on the top. Quantification was continuously achieved in each spot; subsequently, quantitative imaging was realized. Fe and Sr were selected as the model elements, and their spot quantifications based on online-isotope dilution. The method was applied to actual biological hard tissues, and the results were compared with electron probe microanalyzer data.

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

 Times Cited Count:8 Percentile:31.52(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.

JAEA Reports

Preparation of Zr-91 stable isotope standard solution for determination of Zr-93 by mass spectrometry

Konda, Miki; Asai, Shiho; Hanzawa, Yukiko; Magara, Masaaki

JAEA-Technology 2015-054, 22 Pages, 2016/03

JAEA-Technology-2015-054.pdf:3.44MB

Isotope dilution mass spectrometry (IDMS) with ICP-MS is reliable method for determination of Zr-93, which is one of the long-lived fission products found in spent nuclear fuel and high-level radioactive wastes. In order to use an isotope standard solution of zirconium as the spike for IDMS, dissolving a commercially available solid isotope standard is indispensable. Prior to the dissolution of the Zr-91 isotope standard, solubility of metal zirconium in a mixture of HNO$$_3$$ and HF was evaluated using zirconium metal chips. Then, 2 mg of the Zr-91 isotope standard was dissolved with 0.2 mL of 1 M HNO$$_3$$-3 v/v% HF mixed solution, followed by adjusting the concentration of Zr-91 to approximately 1,000 $$mu$$g/g. IDMS, in which a natural isotopic abundance standard solution of zirconium was used as the spike, was employed for the determination of the concentration of Zr-91 in the prepared Zr-91 isotope standard solution. The concentration of Zr-91 in the prepared Zr-91 isotope standard solution was (9.6$$pm$$1.0) $$times$$ 10$$^2$$ $$mu$$g/g, which is in good agreement with the predicted concentration. This indicates that the Zr-91 metal isotope standard was completely dissolved with sufficient chemical stability. Additionally, no impurities were detected in the prepared Zr-91 isotope standard solution. These positive results denote that the Zr-91 isotope standard solution with the preferable quality for IDMS of Zr-93 can be obtained by the proposed dissolution procedures.

Journal Articles

Inherent isotope dilution analysis of $$^{2}$$$$^{3}$$$$^{7}$$Np in spent nuclear fuels

; K.Kammerichs*; L.Koch*

Journal of Radioanalytical and Nuclear Chemistry, Letters, 117(4), p.233 - 241, 1987/04

no abstracts in English

Journal Articles

Journal Articles

Accurate determination of sulfur at trace levels by isotope dilution mass spectrometry

Analytica Chimica Acta, 147, p.417 - 421, 1983/00

 Times Cited Count:11 Percentile:64.37(Chemistry, Analytical)

no abstracts in English

Journal Articles

Determination of molybdenum in nickel-base heat-resisting alloys by isotope dilution mass spectrometry

Mass Spectroscopy, 27(4), p.255 - 261, 1979/00

no abstracts in English

Journal Articles

Isotope dilution method

Kaku Busshitsu Kanri Senta Nyusu, 4(1), p.4 - 5, 1975/01

no abstracts in English

Journal Articles

Determination of sulfur in nickel-base alloys and alloy steels by isotope dilution mass spectrometry

Analytica Chimica Acta, 80, p.117 - 123, 1975/00

 Times Cited Count:13

no abstracts in English

Journal Articles

JAEA Reports

Journal Articles

Determination of hafnium in zircaloy samples by isotope dilution.

; ; *

Bunseki Kagaku, 17(1), p.82 - 85, 1968/00

no abstracts in English

Journal Articles

None

Bunseki Kagaku, 11(7), p.772 - 779, 1962/00

no abstracts in English

Journal Articles

Determination of uranium concentration by isotope dilution method

;

Shitsuryo Bunseki, 9(17), p.37 - 39, 1961/00

no abstracts in English

Oral presentation

Preparation of $$^{91}$$Zr isotope standard solution for isotope dilution mass spectrometry

Konda, Miki; Asai, Shiho; Hanzawa, Yukiko; Magara, Masaaki

no journal, , 

It is important to measure the inventory of radionuclides in high-level radioactive waste for safe and reasonable geological disposal of the waste. For verification of the reliability of the inventory assessment by measured value, we planned to quantify the long-lived nuclides $$^{93}$$Zr, that is important for safety evaluation of radioactive waste disposal, using isotope dilution inductively coupled plasma mass spectrometry (ID-ICP-MS) we developed. Spike (isotope standard solution) is required to apply the IDMS. We prepare $$^{91}$$Zr isotope standard solution by dissolving the metallic $$^{91}$$Zr isotope standard. The metallic Zr dissolves in HF, but HF dissolve glass and has high toxicity. Therefore it is necessary to reduce an amount of HF and to simplify a dissolution method. At first, we examined the dissolution method of the metallic Zr. The isotope standard of $$^{91}$$Zr was dissolved under optimum condition that obtained by the previous examination. The prepared $$^{91}$$Zr isotope standard solution was measured using the IDMS to determine concentration, which gave us a high-accuracy value.

Oral presentation

Performance evaluation of micro-volume anion-exchange filter prepared by graft polymerization on Zr separation and its application to determination of Zr-93 in spent fuel

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

no journal, , 

$$^{93}$$Zr is a long-lived fission product which can be found in spent nuclear fuel and HLW. The estimation of the$$^{93}$$Zr content is indispensable to achieve a safety disposal of HLW because $$^{93}$$Zr is predicted to be one of the major contributors to radiation dose. However, only a few measured $$^{93}$$Zr values have been reported, leading to a high demand for development of an efficient analytical method. Our group has been prepared a new porous filter cartridge which has densely bound ion-exchanger onto the pore surface of the filter, enabling a high-capacity and rapid adsorption. In order to apply this filter cartridge to a pretreatment for the $$^{93}$$Zr measurement with ICP-MS, an elution profiles of Zr and the other coexisting elements were examined. According to the resultant separation conditions, Zr in a spent nuclear fuel sample was successfully separated. The measured $$^{93}$$Zr content is 98.2 $$pm$$ 5.1 ng, which agrees with the theoretical value.

30 (Records 1-20 displayed on this page)