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Do, V. K.; Furuse, Takahiro; Murakami, Erina; Aita, Rena; Ota, Yuki; Sato, Soichi
Journal of Radioanalytical and Nuclear Chemistry, 327(1), p.543 - 553, 2021/01
Times Cited Count:5 Percentile:65.59(Chemistry, Analytical)A new HCl-free chromatographic separation procedure has been developed for sequential separation of Zr and Mo from concrete matrices. Accordingly, Zr and Mo could be sensitively and selectively measured by ICP-MS/MS using ammonia reaction gas. The recoveries of greater than 90% for Zr and Mo from concretes could be achieved. The measurement condition was optimized for complete suppression of interferences from Nb and peak tailing from abundant isotopes of Zr and Mo in concrete matrices. The removal of interferences was verified by measurement of radio-contamination-free concretes used as a sample matrix blank. Method detection limits of 1.7 mBq g and 0.2 Bq g were achieved for Zr and Mo, respectively, in the concrete matrices. The interference removal factor for Nb (equivalent to the decontamination factor in radiochemical separation) was of the order of 10, and the abundance sensitivity was of the order of 10, indicating that the developed method is reliable for verifying the presence of ultralow concentrations of Zr and Mo. The present method is suitable for the rapid assessment of Zr and Mo for radioactivity inventory of concrete rubble.
Koma, Yoshikazu; Murakami, Erina
Radiochimica Acta, 107(9-11), p.965 - 977, 2019/09
Times Cited Count:1 Percentile:11.15(Chemistry, Inorganic & Nuclear)Fukushima Daiichi Nuclear Power Station, which is owned by Tokyo Electric Power Company, suffered from the great earthquake and Tsunami on 11 March 2011, and serious contamination with radioactive nuclides occurred. To investigate methodologies of waste management, contaminated materials have been radiochemically analyzed. This paper reviews the analytical data for actinide elements. Actinide nuclides are detected in the contaminated water. The contaminated water is chemically decontaminated, although actinide concentration does not decrease with time. This suggests that actinides come from the damaged fuel with slow dissolution. From the topsoil at the site, Pu, Am and Cm were detected and come from the damaged fuel, whereas U from natural. TRU would slowly move to deeper. Contamination of rubble is nonuniform and actinides are detected as well as fission products. For vegetation, TRU nuclides were found from fallen leaves near the reactor buildings.
Murakami, Erina; Oki, Keiichi; Takahatake, Yoko; Nitta, Ayako; Shibata, Atsuhiro; Koma, Yoshikazu
no journal, ,
no abstracts in English
Do, V. K.; Furuse, Takahiro; Murakami, Erina; Aita, Rena; Ota, Yuki; Tomitsuka, Tomohiro; Sano, Yuichi; Akimoto, Yuji*; Endo, Tsubasa*; Katayama, Atsushi; et al.
no journal, ,
The paper presents removal of possible interferences including from an isobar (Nb) and tailings of adjacent peaks for the quantification of Zr and Mo using an ICP-MS/MS (Agilent 8900). By using ammonia gas (NH) as a reaction gas, Zr and Mo can be separated from each other and from Nb owing to the different reactions of those elements with the reaction gas. Based on the characterization results, we propose a measurement scheme aiming at quantification of Zr and Mo in environmental samples collected at adjacent location of Fukushima Daiichi Nuclear Power Station.
Furuse, Takahiro; Do, V. K.; Aita, Rena; Ota, Yuki; Murakami, Erina; Tomitsuka, Tomohiro; Sano, Yuichi; Akimoto, Yuji*; Endo, Tsubasa*; Katayama, Atsushi; et al.
no journal, ,
In order to simplify the analysis of Zr and Mo in radioactive waste from conventional radiation measurement, we have considered analysis method combining solid-phase extraction and ICP-MS/MS. In this presentation, we report the results of a study on sequential chemical separation of Zr and Mo from Nb and sample matrix using ZR resin as a solid-phase extraction resin.
Tanaka, Masaaki; Kikuchi, Norihiro; Hamase, Erina; Murakami, Satoshi*; Fujisaki, Tatsuya*; Imai, Yasutomo*
no journal, ,
For safety enhancement of sodium-cooled fast reactor, decay heat removal system (DHRS) by using the natural circulation without depending on the pump as the mechanical equipment is recognized as one of the most effective method. The numerical estimation method which can predict thermal hydraulic phenomena in the reactor vessel during DHRS operation is necessarily required. In this study, appropriate modeling to predict the inter wrapper flow which is caused in the gap between fuel subassemblies is preliminary investigated. The validation of the numerical results is carried out in comparison with the measured temperature data in the scaled sodium test facility named PLANDTL-1. Through the simulation, potential applicability of the gap model using the correlation equations to simulate the thermal hydraulics behavior of the inter-wrapper flow in the core is indicated.
Do, V. K.; Ota, Yuki; Banjarnahor, I. M.; Aita, Rena; Murakami, Erina; Homma, Shunta; Iwahashi, Hiroyuki; Furuse, Takahiro
no journal, ,
The Okuma Analysis and Research Center has been established to analyze the decommissioning wastes collected from Fukushima Daiichi Nuclear Power Plant (1F). Radioactive material analysis and research facility 1 (Laboratory-1) where analyses of the low and intermediate-level wastes are preliminarily tested has started the operation from October 2022. Among the selected radionuclides to be analyzed, long-lived radionuclides can be measured by inductively coupled plasma mass spectrometry, which offers more rapid measurement and higher sensitivity compared to radiometry. The modern configuration of tandem triple quadrupoles (called ICP-QQQ-MS or ICP-MS/MS) enables the effective control of interferences that can simplify the chemical separation process and thus reduces the total time of analysis. The presentation summarizes our recent advances in research and development of analytical methods for the selected long-lived radionuclides such as Zr, Mo, Pd, Sn, and Se by ICP-MS/MS, aiming at applications to the measurement of samples collected in the vicinity of 1F. The analytical method development and recently obtained results are discussed in detail.