Development of a separation method for molybdenum from zirconium, niobium, and major elements of rubble samples

Shimada, Asako; Ozawa, Mayumi; Yabuki, Koshi; Kimiyama, Kazuhiro; Satô, Kenji; Kameo, Yutaka

doi:10.1016/j.chroma.2014.10.053

Cited by 16 publications

(11 citation statements)

References 14 publications

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“…In addition, other anion radionuclides such as 99 TcO 4 – and 36 Cl – presenting in the sample will flow into effluent, which have to be removed from 93 Mo before measurement. Chromatographic methods using anion exchange and TEVA resin have been reported for the separation of Mo from other anions in HCl, HNO 3 , and HF media, − , but none of them could be applied in H 2 SO 4 media (see detailed discussion in Sections 4 and 5 in Supporting Information). Therefore, H 2 SO 4 or SO 4 2– in the obtained solution from cation exchange column has to be removed before further separation of Mo.…”

Section: Resultsmentioning

confidence: 99%

“…A few separation methods (summarized in Table S1 in Supporting Information) have been reported for the determination of 93 Mo in rubble, metal, contaminated water samples, and irradiated 93 Nb target ,, using precipitation, ion exchange chromatography, , extraction chromatography with TEVA resin, − and alumina column, , in HCl, HNO 3 , and HF media. ,− Among them, the application HF makes the operation more difficult in glove box and fume hood because no glassware can be used and no HF could be released to the ventilation system. Our preliminary experiment also showed that all these methods could not be used for the separation of molybdenum from H 2 SO 4 media, because MoO 4 2– in SO 4 2– media could not be adsorbed on TEVA, anion exchange resin, and alumina.…”

Section: Introductionmentioning

confidence: 99%

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Determination of ⁹³Mo in Radioactive Samples of Sulfuric Acid Media from Nuclear Facilities

et al. 2022

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93 Mo is an important radionuclide in view of radioactive waste repository because of its long half-life and high mobility in the environment. 93 Mo decays by electron capture without any measurable gamma ray emission. The concentration of 93 Mo in most of the radioactive waste is many orders of magnitude lower than the major activation product radionuclides, which makes the accurate determination of 93 Mo a big challenge. A new analytical method for the determination of 93 Mo in sulfuric acid media from nuclear power reactor was developed. 93 Mo was separated from most of the radionuclides by cation exchange chromatography followed by the removal of sulfate by CaSO 4 precipitation. A further purification of 93 Mo, especially from anion species of 51 Cr and 125 Sb, was achieved by anion exchange chromatography and a short alumina column separation. The chemical yield of 93 Mo in the entire separation procedure reached about 75%, and the decontamination factors for all potential interfering radionuclides were 1.5 × 10 6 −1.6 × 10 8 . The purified 93 Mo was measured by liquid scintillation counting through counting its low-energy Auger electrons. A detection limit of 2 mBq/g for 93 Mo in 50 g sample was achieved by this method, which enables the quantitative determination of 93 Mo in most of the radioactive samples in the decommissioning waste and coolant water of nuclear power reactors. The developed method has been successfully applied to determine 93 Mo in coolant water of nuclear power reactors, providing a robust analytical approach of 93 Mo for the radiological characterization of radioactive wastes. 93

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Section: Resultsmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

Determination of ⁹³Mo in Radioactive Samples of Sulfuric Acid Media from Nuclear Facilities

et al. 2022

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“…Previously, separation method for Mo using a TEVA resin was developed to purify Mo from rubble samples 35 . Because the dissolved solution of the rubble sample contained large amount of Fe 3+ and Cr 6+ , which compete with Mo extraction on the TEVA resin, ascorbic acid was added to the sample solution to decrease their extraction by reducing to Fe 2+ and Cr 3+ .…”

Section: Materials and Analysis Methodsmentioning

confidence: 99%

Radiochemical analysis of the drain water sampled at the exhaust stack shared by Units 1 and 2 of the Fukushima Daiichi Nuclear Power Station

Shimada

Taniguchi

Kakiuchi

et al. 2022

Sci Rep

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Radioactive gas of Unit 1 of the Fukushima Daiichi Nuclear Power Station was released from the exhaust stack shared by Units 1 and 2 through the venting line on March 12th, 2011. In the present study, radiochemical analysis of drain water sampled at the drain pit of the exhaust stack was conducted to study radionuclides released during venting of the Unit 1. Not only volatile 129I, 134Cs and 137Cs but also 60Co, 90Sr, 125Sb and Unit 1-originated stable Mo isotopes were detected. Although Unit 1-originated stable Mo isotopes were clearly detected, their amounts were quite low compared to Cs, suggesting that the formation of Cs2MoO4 was suppressed under the accident condition. Approximately 90% of iodine existed as I− and 10% as IO3− in November 2020. Furthermore, larger amount of 129I than 137Cs was observed, suggesting major chemical form of 131I was molecular iodine rather than CsI at the accident time. The 134Cs/137Cs radioactivity ratio decay-corrected to March 11th, 2011 was 0.86, supported the results that Unit 1 originated radiocesium in environment has smaller 134Cs/137Cs radioactivity ratio than Unit 2 and 3 originated radiocesium.

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“…However, it was reported that the recovery of Mo was unsatisfying using a method based on this feature [16]. Shimada reported two methods to separate Mo from -among others -Nb using TEVA resin [5,17]. The major drawback of these methods is the unsatisfying decontamination of Nb in the Mo fraction.…”

Section: Introductionmentioning

confidence: 99%

Preparation of 93Mo solution using proton irradiated Nb

Osváth

Qiao

Hou

2019

J Radioanal Nucl Chem

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93 Mo is an important long-lived radionuclide in nuclear waste, and is required to be measured during the characterization of decommissioning waste. However, no commercial 93 Mo solution is available to be calibrated and used as standard in the analysis of nuclear waste. This work presents a method for separation of 93 Mo from Nb metal used in cyclotron as a target holder and irradiated with protons for long time. The separation of 93 Mo from Nb matrix was implemented by combination of precipitation and chromatographic separation. The Nb matrix was first removed by precipitating oxides-hydroxides of Nb (e.g. Nb 2 O 5) and then by Fe(OH) 3 co-precipitation; Mo in the solution was purified using an alumina (Al 2 O 3) column. A decontamination factor of ca. 10 5 was achieved for Nb. A pure carrier-free 93 Mo solution was successfully prepared, and the 93 Mo purity was verified by liquid scintillation spectrometry. Keywords 93 Mo • Nb • Separation • Nb 2 O 5 /Fe(OH) 3 precipitation • Alumina (Al 2 O 3) column • LSC

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Development of a separation method for molybdenum from zirconium, niobium, and major elements of rubble samples

Cited by 16 publications

References 14 publications

Determination of ⁹³Mo in Radioactive Samples of Sulfuric Acid Media from Nuclear Facilities

Determination of ⁹³Mo in Radioactive Samples of Sulfuric Acid Media from Nuclear Facilities

Radiochemical analysis of the drain water sampled at the exhaust stack shared by Units 1 and 2 of the Fukushima Daiichi Nuclear Power Station

Preparation of 93Mo solution using proton irradiated Nb

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Development of a separation method for molybdenum from zirconium, niobium, and major elements of rubble samples

Cited by 16 publications

References 14 publications

Determination of 93Mo in Radioactive Samples of Sulfuric Acid Media from Nuclear Facilities

Determination of 93Mo in Radioactive Samples of Sulfuric Acid Media from Nuclear Facilities

Radiochemical analysis of the drain water sampled at the exhaust stack shared by Units 1 and 2 of the Fukushima Daiichi Nuclear Power Station

Preparation of 93Mo solution using proton irradiated Nb

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Product

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Determination of ⁹³Mo in Radioactive Samples of Sulfuric Acid Media from Nuclear Facilities

Determination of ⁹³Mo in Radioactive Samples of Sulfuric Acid Media from Nuclear Facilities