利用MIPR生产^(99)Mo、^(131)I和^(89)Sr的可行性研究  

Feasibility Research of ^(99)Mo,^(31)I and ^(89)Sr Production by Medical Isotope Production Reactor

作　　者：邓启民[1] 程作用[1] 李茂良[1] 张劲松[2] 陈云明[2] 

机构地区：[1]中国核动力研究设计院成都云克药业有限责任公司,成都610041 [2]中国核动力研究设计院反应堆运行与应用研究所,成都610041

出　　处：《核动力工程》2011年第6期115-118,124,共5页Nuclear Power Engineering

摘　　要：利用模拟的医用同位素生产堆(MIPR)液体回路输送系统进行提取99Mo和131I的研究,并在模拟的气体回路系统中进行提取气态131I和89Sr并纯化的研究。结果表明,从模拟的MIPR燃料溶液中提取99Mo和131I产品的回收率分别为56.4%和50.2%,产品的质量满足药典标准的要求;模拟的气体回路中的131I可以用吸附剂提取,回收率达到90%以上;在气体回路旁路中提取的89Sr可以采用化学分离方法进行纯化,回收率达到70%;MIPR可以用于99Mo、131I和89Sr的生产。The recovery of 99Mo and 131I was studied from simulation of Medical Isotope Production Reactor（MIPR） loop liquid delivery system,and the 131I recovery and 89Sr purification from simulation of MIPR gaseous loop.The results indicated that the overall recovery yield of 99Mo and 131I from simulation liquid delivery system were 56.4% and 50.2% respectively,while the contents of impurities meet Pharmacopoeia require.131I in gaseous loop can be recovered with absorbent,and the recovery yield is more than 90%.The 89Sr recovered from by-pass gaseous loop can be purified by chemical separation,and the over all recovery yield of strontium is more than 70%,while the contents of impurities meet Pharmacopoeia re-quire.The results showed that MIPR can be used for 99Mo,131I and 89Sr production.

关 键 词：医用同位素生产堆 99Mo 131I 89Sr 提取 纯化 

分 类 号：TL922[核科学技术—核燃料循环与材料]