钍铀燃料对微型反应堆中子源生产医用核素的影响  

The Impact of Thorium-Uranium Fuel on the Production of Medical Nuclides in Micro Nuclear Source Reactor

作　　者：张子雄 王佳[1,2] 李凯旋 潘炀烜 魏强林 刘义保[1,2,3] ZHANG Zixiong;WANG Jia;LI Kaixuan;PAN Yangxuan;WEI Qianglin;LIU Yibao(Engineering Research Center of Nuclear Technology Application,Ministry of Education,East China University of Technology,Nanchang 330013,China;School of Nuclear Science and Engineering,East China University of Technology,Nanchang 330013,China;Jiangxi Engineering Research Center for Nuclear Radiation Detection and Application,Nanchang 330013,China)

机构地区：[1]东华理工大学核技术应用教育部工程研究中心,江西南昌330013 [2]东华理工大学核科学与工程学院,江西南昌330013 [3]江西省核辐射探测及应用工程技术研究中心,江西南昌330013

出　　处：《东华理工大学学报(自然科学版)》2025年第2期166-173,共8页Journal of East China University of Technology(Natural Science)

基　　金：核技术应用教育部工程研究中心开放基金项目(HJSJYB 2021-9);东华理工大学博士科研启动基金项目(DHBK2021005);江西省质谱科学与仪器重点实验室开放基金项目(JXMS202111)。

摘　　要：随着高通量核反应堆的退役和放射性同位素需求的增长,同位素供应问题日益严峻。微型反应堆以其结构简单、安全可靠、建造和运行成本低等特点,有潜力成为新一代医用同位素的生产装置。利用微型反应堆中子源(MNSR)建立中子辐照生产模型,采用天然氧化物材料(MoO_(3)、Lu 2O_(3)、Y 2O_(3))进行辐照生产模拟。研究结果表明,ThO_(2)的掺入可以一定程度上提高中子通量和热化效果,从而增强医用同位素的生产能力。同时ThO_(2)的掺入并未削弱燃料的负反馈特性,从而维持了堆芯的安全性。在钍铀比为5∶100的条件下,单日辐照可获得2.18 mCi/g的99 Mo、74.32 mCi/g的177 Lu以及41.56 mCi/g的90 Y。研究旨在提高钍资源的利用效率和同位素生产效率,为解决医用核素供应问题提供一种可行的解决方案。With the decommissioning of high-flux nuclear reactors and the increasing demand for radioisotopes,the isotope supply has become increasingly critical.Miniature nuclear reactors,characterized by their simple structure,high safety,and low construction and operational costs,hold potential as the next generation of production facilities for medical radioisotopes.A Miniature Neutron Source Reactor(MNSR)was utilized to establish a neutron irradiation production model,employing natural oxide materials(MoO_(3),Lu 2O_(3),Y_(2)O_(3))for irradiation production.The results indicate that the incorporation of thorium dioxide(ThO_(2))significantly enhances neutron flux and thermalization,thereby augmenting the production capacity of medical radioisotopes.Concurrently,the addition of ThO_(2)did not compromise the fuels negative feedback characteristics,ensuring the safety of the reactor core.Under a thorium-to-uranium ratio of 5∶100,daily irradiation yields of 2.18 mCi/g for 99 Mo,74.32 mCi/g for 177 Lu,and 41.56 mCi/g for 90 Y were achieved.The research aims to improve the utilization efficiency of thorium resources and the efficiency of radioisotope production,offering a viable solution to the supply problem of medical radionuclides.

关 键 词：钍铀燃料 微型反应堆 中子源 医用同位素 

分 类 号：TL92[核科学技术—核燃料循环与材料]