Preparation of 93Mo solution using proton irradiated Nb

Szabolcs Osváth; Jixin Qiao; Xiaolin Hou

doi:10.1007/s10967-019-06758-5

Preparation of ⁹³Mo solution using proton irradiated Nb

Szabolcs Osváth^*, Jixin Qiao, Xiaolin Hou

^*Corresponding author for this work

Research output: Contribution to journal › Journal article › Research › peer-review

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Abstract

⁹³Mo is an important long-lived radionuclide in nuclear waste, and is required to be measured during the characterization of decommissioning waste. However, no commercial ⁹³Mo solution is available to be calibrated and used as standard in the analysis of nuclear waste. This work presents a method for separation of ⁹³Mo from Nb metal used in cyclotron as a target holder and irradiated with protons for long time. The separation of ⁹³Mo 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. Nb₂O₅) and then by Fe(OH)₃ co-precipitation; Mo in the solution was purified using an alumina (Al₂O₃) column. A decontamination factor of ca. 10⁵ was achieved for Nb. A pure carrier-free ⁹³Mo solution was successfully prepared, and the ⁹³Mo purity was verified by liquid scintillation spectrometry.

Original language	English
Journal	Journal of Radioanalytical and Nuclear Chemistry
Volume	322
Issue number	3
Pages (from-to)	1833–1839
ISSN	0236-5731
DOIs	https://doi.org/10.1007/s10967-019-06758-5
Publication status	Published - 2019

Keywords

93Mo
Nb
Separation
Nb2O5/Fe(OH)3 precipitation
Alumina (Al2O3) column
LSC

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title = "Preparation of 93Mo solution using proton irradiated Nb",

abstract = " 93Mo is an important long-lived radionuclide in nuclear waste, and is required to be measured during the characterization of decommissioning waste. However, no commercial 93Mo solution is available to be calibrated and used as standard in the analysis of nuclear waste. This work presents a method for separation of 93Mo from Nb metal used in cyclotron as a target holder and irradiated with protons for long time. The separation of 93Mo 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. Nb2O5) and then by Fe(OH)3 co-precipitation; Mo in the solution was purified using an alumina (Al2O3) column. A decontamination factor of ca. 105 was achieved for Nb. A pure carrier-free 93Mo solution was successfully prepared, and the 93Mo purity was verified by liquid scintillation spectrometry.",

keywords = "93Mo, Nb, Separation, Nb2O5/Fe(OH)3 precipitation, Alumina (Al2O3) column, LSC",

author = "Szabolcs Osv{\'a}th and Jixin Qiao and Xiaolin Hou",

year = "2019",

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TY - JOUR

T1 - Preparation of 93Mo solution using proton irradiated Nb

AU - Osváth, Szabolcs

AU - Qiao, Jixin

AU - Hou, Xiaolin

PY - 2019

Y1 - 2019

N2 - 93Mo is an important long-lived radionuclide in nuclear waste, and is required to be measured during the characterization of decommissioning waste. However, no commercial 93Mo solution is available to be calibrated and used as standard in the analysis of nuclear waste. This work presents a method for separation of 93Mo from Nb metal used in cyclotron as a target holder and irradiated with protons for long time. The separation of 93Mo 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. Nb2O5) and then by Fe(OH)3 co-precipitation; Mo in the solution was purified using an alumina (Al2O3) column. A decontamination factor of ca. 105 was achieved for Nb. A pure carrier-free 93Mo solution was successfully prepared, and the 93Mo purity was verified by liquid scintillation spectrometry.

AB - 93Mo is an important long-lived radionuclide in nuclear waste, and is required to be measured during the characterization of decommissioning waste. However, no commercial 93Mo solution is available to be calibrated and used as standard in the analysis of nuclear waste. This work presents a method for separation of 93Mo from Nb metal used in cyclotron as a target holder and irradiated with protons for long time. The separation of 93Mo 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. Nb2O5) and then by Fe(OH)3 co-precipitation; Mo in the solution was purified using an alumina (Al2O3) column. A decontamination factor of ca. 105 was achieved for Nb. A pure carrier-free 93Mo solution was successfully prepared, and the 93Mo purity was verified by liquid scintillation spectrometry.

KW - 93Mo

KW - Nb

KW - Separation

KW - Nb2O5/Fe(OH)3 precipitation

KW - Alumina (Al2O3) column

KW - LSC

U2 - 10.1007/s10967-019-06758-5

DO - 10.1007/s10967-019-06758-5

M3 - Journal article

SN - 0236-5731

VL - 322

SP - 1833

EP - 1839

JO - Journal of Radioanalytical and Nuclear Chemistry

JF - Journal of Radioanalytical and Nuclear Chemistry

IS - 3

ER -