Research on the Production Process of 99Mo Based on Low Enriched Uranium Fuel in Medical Isotope Test Reactor

The medical isotope test reactor that utilizes uranyl nitrate solution as its fuel source has certain advantages when it comes to the production of 99Mo. This method has emerged as an important developmental direction for the generation of medical isotopes. Low-enriched uranium fuel is the trend of...

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Main Authors: Haijun WANG, Zhizhong SUN, Zisheng GENG, Keyu LUO, Yu DENG, Yunming CHEN, Ning LUO, Jinsong ZHANG
Format: Article
Language:zho
Published: Editorial Board of Journal of Isotopes 2025-02-01
Series:Journal of Isotopes
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Online Access:https://tws.xml-journal.net/article/doi/10.7538/tws.2024.youxian.077
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author Haijun WANG
Zhizhong SUN
Zisheng GENG
Keyu LUO
Yu DENG
Yunming CHEN
Ning LUO
Jinsong ZHANG
author_facet Haijun WANG
Zhizhong SUN
Zisheng GENG
Keyu LUO
Yu DENG
Yunming CHEN
Ning LUO
Jinsong ZHANG
author_sort Haijun WANG
collection DOAJ
description The medical isotope test reactor that utilizes uranyl nitrate solution as its fuel source has certain advantages when it comes to the production of 99Mo. This method has emerged as an important developmental direction for the generation of medical isotopes. Low-enriched uranium fuel is the trend of research reactor development,and the 99Mo separation process of the medical isotope test reactor under low-enriched uranium conditions is crucial. In this study,a comprehensive analysis was conducted on the 99Mo separation and purification process using a medical isotope test reactor that utilizes low-enriched uranium fuel. The research primarily focused on the development and optimization of a novel method involving a combination of spherical alumina columns,an α-benzoin oxime column,and an activated carbon column. The outcomes of this research are promising,as the combination of these three columns facilitated an effective extraction,separation,and purification of 99Mo. Moreover,through the production verification of the separation of Mo in the low-enriched uranium simulated fuel solution by using this process,the recovery rate of Mo is 75.7%,and the impurities also meet the requirements. This process improves the production rate of 99Mo of the medical isotope test reactor under low-enriched uranium fuel conditions,lays a foundation for the low-enrichment of the medical isotope test reactor,and has great application value.
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spelling doaj-art-696de2f6587340bbbc69f743a77f94572025-01-24T06:37:08ZzhoEditorial Board of Journal of IsotopesJournal of Isotopes1000-75122025-02-01381222910.7538/tws.2024.youxian.077202407077Research on the Production Process of 99Mo Based on Low Enriched Uranium Fuel in Medical Isotope Test ReactorHaijun WANG0Zhizhong SUN1Zisheng GENG2Keyu LUO3Yu DENG4Yunming CHEN5Ning LUO6Jinsong ZHANG7China Nuclear Power Research and Design Institute, Chengdu 610213, ChinaChina Nuclear Power Research and Design Institute, Chengdu 610213, ChinaChina Nuclear Power Research and Design Institute, Chengdu 610213, ChinaChina Nuclear Power Research and Design Institute, Chengdu 610213, ChinaChina Nuclear Power Research and Design Institute, Chengdu 610213, ChinaChina Nuclear Power Research and Design Institute, Chengdu 610213, ChinaChina Nuclear Power Research and Design Institute, Chengdu 610213, ChinaChina Nuclear Power Research and Design Institute, Chengdu 610213, ChinaThe medical isotope test reactor that utilizes uranyl nitrate solution as its fuel source has certain advantages when it comes to the production of 99Mo. This method has emerged as an important developmental direction for the generation of medical isotopes. Low-enriched uranium fuel is the trend of research reactor development,and the 99Mo separation process of the medical isotope test reactor under low-enriched uranium conditions is crucial. In this study,a comprehensive analysis was conducted on the 99Mo separation and purification process using a medical isotope test reactor that utilizes low-enriched uranium fuel. The research primarily focused on the development and optimization of a novel method involving a combination of spherical alumina columns,an α-benzoin oxime column,and an activated carbon column. The outcomes of this research are promising,as the combination of these three columns facilitated an effective extraction,separation,and purification of 99Mo. Moreover,through the production verification of the separation of Mo in the low-enriched uranium simulated fuel solution by using this process,the recovery rate of Mo is 75.7%,and the impurities also meet the requirements. This process improves the production rate of 99Mo of the medical isotope test reactor under low-enriched uranium fuel conditions,lays a foundation for the low-enrichment of the medical isotope test reactor,and has great application value.https://tws.xml-journal.net/article/doi/10.7538/tws.2024.youxian.07799momedical isotope test reactors99mo preparation processspherical aluminaα-benzoin oxime
spellingShingle Haijun WANG
Zhizhong SUN
Zisheng GENG
Keyu LUO
Yu DENG
Yunming CHEN
Ning LUO
Jinsong ZHANG
Research on the Production Process of 99Mo Based on Low Enriched Uranium Fuel in Medical Isotope Test Reactor
Journal of Isotopes
99mo
medical isotope test reactors
99mo preparation process
spherical alumina
α-benzoin oxime
title Research on the Production Process of 99Mo Based on Low Enriched Uranium Fuel in Medical Isotope Test Reactor
title_full Research on the Production Process of 99Mo Based on Low Enriched Uranium Fuel in Medical Isotope Test Reactor
title_fullStr Research on the Production Process of 99Mo Based on Low Enriched Uranium Fuel in Medical Isotope Test Reactor
title_full_unstemmed Research on the Production Process of 99Mo Based on Low Enriched Uranium Fuel in Medical Isotope Test Reactor
title_short Research on the Production Process of 99Mo Based on Low Enriched Uranium Fuel in Medical Isotope Test Reactor
title_sort research on the production process of 99mo based on low enriched uranium fuel in medical isotope test reactor
topic 99mo
medical isotope test reactors
99mo preparation process
spherical alumina
α-benzoin oxime
url https://tws.xml-journal.net/article/doi/10.7538/tws.2024.youxian.077
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