Study on measurement of fission product nuclide 126Sn by AMS

Shen, Hongtao; Jiang, Shan; He, Ming; Dong, Kun; Chaoli, Li; He, Guo‐Zhong; Wu, Shich-Chuan; Gong, Jie; Lu, Liyan; Li, Shizhuo; Zhang, Dawei; Shi, Guozhu; Chun-Tang, Huang; Wu, Shaoyong

doi:10.1016/j.nimb.2010.11.059

Cited by 7 publications

(1 citation statement)

References 13 publications

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“…The previous studies on 126 Sn measurement were mainly intended to confirm its half life. Various purification procedures have been reported for activity measurement by gamma spectrometry and mass measurement by accelerator mass spectrometry (AMS) [3][4][5], thermal ionization MS [6] and inductively coupled plasma-MS (ICP-MS) [7,8]. Zhang [3].…”

Section: Introductionmentioning

confidence: 99%

Isotope dilution inductively coupled plasma mass spectrometry for determination of¹²⁶Sn content in spent nuclear fuel sample

Asai

Toshimitsu

Hanzawa

et al. 2013

Journal of Nuclear Science and Technology

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The 126 Sn content in a spent nuclear fuel solution was determined by isotope dilution inductively coupled plasma mass spectrometry (ID-ICP-MS) for its inventory estimation in high-level radioactive waste. A well-characterized irradiated UO 2 fuel sample dissolved in a hot cell was used as a sample to evaluate the reliability of the methodology. Prior to the ICP-MS measurement, Sn was separated from Te ( 126 Te), which causes major isobaric interference in the determination of 126 Sn content, along with highly radioactive coexisting elements, such as Sr ( 90 Sr), Y ( 90 Y), Cs ( 137 Cs) and Ba ( 137m Ba), using an anionexchange column. The absence of counts attributed to Te at m/z = 125, 128, and 130 in the Sn-containing effluent (Sn fraction) indicates that Te was completely removed from the anion-exchange column. After washing, Sn retained on the column was readily eluted with 1 M HNO 3 accompanied with approximately 80% of the Cd and 0.03% of the U in the initial sample. Owing to the presences of Cd and U in Sn fraction, the measurements of 116 Sn and 119 Sn were affected by the isobaric 116 Cd and the doubly charged 238 U 2 + ion, resulting in the positive bias of the determined values. With the exception of the isotopic ratios including 116 Sn and 119 Sn, 117 Sn/ 126 Sn, 118 Sn/ 126 Sn, 120 Sn/ 126 Sn, 122 Sn/ 126 Sn and 124 Sn/ 126 Sn were successfully determined and showed good agreement with those obtained through ORIGEN2 calculations. The measured concentration of 126 Sn in the spent nuclear fuel sample solution was 0.74 ± 0.14 ng/g, which corresponds to 23.0 ± 4.5 ng per gram of the irradiated UO 2 fuel (excluding the presence of 126 Sn in the insoluble residue). The results reported in this paper are the first experimental values of 126 Sn content and isotope ratios in the spent nuclear fuel solution originating in spent nuclear fuel irradiated at a nuclear power plant in Japan.

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Section: Introductionmentioning

confidence: 99%

Isotope dilution inductively coupled plasma mass spectrometry for determination of¹²⁶Sn content in spent nuclear fuel sample

Asai

Toshimitsu

Hanzawa

et al. 2013

Journal of Nuclear Science and Technology

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Determination of 126Sn in radioactive waste using TEVA® resin and gamma spectrometry

Dulanská

Bilohuščin

Remenec

et al. 2015

J Radioanal Nucl Chem

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Development of HCl-free solid-phase extraction combined with ICP-MS/MS for rapid assessment of difficult-to-measure radionuclides. Part II: Highly sensitive monitoring of 126Sn in concrete rubble

Khoai

Furuse²,

Ohta³

et al. 2022

J Radioanal Nucl Chem

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Study on measurement of fission product nuclide 126Sn by AMS

Cited by 7 publications

References 13 publications

Isotope dilution inductively coupled plasma mass spectrometry for determination of¹²⁶Sn content in spent nuclear fuel sample

Isotope dilution inductively coupled plasma mass spectrometry for determination of¹²⁶Sn content in spent nuclear fuel sample

Determination of 126Sn in radioactive waste using TEVA® resin and gamma spectrometry

Development of HCl-free solid-phase extraction combined with ICP-MS/MS for rapid assessment of difficult-to-measure radionuclides. Part II: Highly sensitive monitoring of 126Sn in concrete rubble

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Study on measurement of fission product nuclide 126Sn by AMS

Cited by 7 publications

References 13 publications

Isotope dilution inductively coupled plasma mass spectrometry for determination of126Sn content in spent nuclear fuel sample

Isotope dilution inductively coupled plasma mass spectrometry for determination of126Sn content in spent nuclear fuel sample

Determination of 126Sn in radioactive waste using TEVA® resin and gamma spectrometry

Development of HCl-free solid-phase extraction combined with ICP-MS/MS for rapid assessment of difficult-to-measure radionuclides. Part II: Highly sensitive monitoring of 126Sn in concrete rubble

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Isotope dilution inductively coupled plasma mass spectrometry for determination of¹²⁶Sn content in spent nuclear fuel sample

Isotope dilution inductively coupled plasma mass spectrometry for determination of¹²⁶Sn content in spent nuclear fuel sample