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医用放射性同位素99Mo/99mTc生产现状和展望

Production Status and Technical Prospects of Medical Radioisotope 99Mo/99mTc

  • 摘要: 99mTc是目前临床诊断应用最为广泛的医用放射性同位素。现有医用99mTc主要通过在实验堆中辐照高浓缩235U生成的99Mo衰变得到,存在工艺复杂、成本高、长距离运输损失等弊端以及核扩散风险。此外,全球实验反应堆为数不多且面临老化、退役问题,也多次因计划内的维修或意外停产事件而使99mTc供应面临困难。本文从99Mo/99mTc的供求现状入手,分析了目前供应链中存在的主要问题,重点介绍了六种传统及新型99Mo/99mTc生产技术的原理、研究进展及其经济性效益。详细评述了三种99Mo/99mTc分离纯化工艺,提出了99Mo/99mTc生产的发展趋势和展望。其中,以加速器驱动裂变低浓缩铀盐溶液的生产方式具有无反应堆、无高浓缩铀、放射性废物少等优势,是未来的重点研究方向。同时,为减少99Mo/99mTc损失,提高产品质量,开发和优化与生产体系相适应的分离纯化工艺也势在必行。中国科学院核能安全技术研究所FDS中科凤麟核能团队设计开发的一种氘氚聚变中子源驱动的99Mo次临界生产系统方案,可获得27Ci/d的99Mo产量,能满足国内一个中等省份的医疗诊断需求。

     

    Abstract: Currently the 99mTc is most widely used medical radioisotope as a tracer in clinical diagnosis. The supply of the 99mTc mainly depends on the production of the 99Mo in the research reactors by irradiating High Enriched Uranium targets. The traditional production technique has disadvantages of complex process, high cost, long-distance transportation loss and the risk of nuclear weapons proliferation, etc. In addition, the number of research reactors and processing facilities are limited and most of the facilities will be decommissioned soon. Sometime the supply of 99Mo/99mTc has a problem due to unexpected reactor shutdown or planned maintenance. So, during recent years, a variety of new production techniques, such as the methods using facilities of linear/cyclotron accelerators and new types of reactors, have been proposed to restore the stable supply of 99Mo/99mTc. Starting from the current supply and demand situation of 99Mo/99mTc, this paper analyses the main problems existing in the current supply chain, and mainly introduces the principle, research progress and economic benefits of six traditional and new production technologies of 99Mo/99mTc. Following three separation and purification processes of 99Mo/99mTc, the development trend and prospect of 99Mo/99mTc production were discussed. Among them, the technology of accelerator-driven fission low-enriched-uranium solution is the key research direction in the future for no reactor, no high-enriched uranium, less radioactive waste. It is also imperative to develop and optimize the separation and purification process suitable for the production system in order to reduce the loss of 99Mo/99mTc and improve product quality. The theoretical output of the99Mo sub-critical production system driven by the deuterium-tritium fusion neutron source, designed by the Institute of Nuclear Safety Technology of the Chinese Academy of Sciences, is 27 Ci/day, which can meet the medical diagnostic needs of a province in China.

     

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