摘要
233 U比235 U具有更好的燃料特性,是具有潜在重要应用价值的核燃料,但直接使用钍铀或钍钚混合燃料在堆中辐照得到的233 U,含有大量的232 U及234 U,放射性较强,难以像235 U一样作为常规核燃料使用。基于低放射性233 U的制备需求,本文分析了232 Th-233 U转化中U同位素杂质232 U及234 U的产生途径,采用可有效减少232 U生成的热堆辐照思路,研究了热堆制备低放射性233 U的辐照工艺。利用MCNP程序对232 Th样品在西安脉冲堆堆内辐照过程进行建模,分析了辐照时间、冷却时间、多个“辐照-冷却”周期法辐照及中间产物230 Th对辐照产物的影响,给出了西安脉冲堆制备低放射性233 U辐照工艺。研究结果表明,本文制备的低放射性233 U产品中233 U的质量分数为10^-5量级,232 U、234 U与233 U的质量比分别小于10^-6和10^-3,符合低放射性233 U指标要求。
233 U has a better fission characteristic than 235 U,and it is a potentially important nuclear fuel.Based on the preparation requirement of low radiation 233 U irradiation process,the production path of isotope impurity of 232 U and 234 U in the conversion of 232 Th to 233 U is analyzed.The irradiation process of 232 Th samples on Xi’an Pulsed Reactor is modeled by using MCNP code.The effects of irradiation time,cooling time,the multiple“irradiation-cooling”cycles,and 230 Th on the irradiated products are analyzed.A low radiation 233 U irradiation process on Xi’an Pulsed Reactor is given.The results showed that the mass of low radiation 233 U is 10^-5,the mass ratios of 232 U,234 U to 233 U are below 10^-6 and 10^-3,respectively,while the product meets the low radiation 233 U standard.
作者
朱养妮
长孙永刚
郭和伟
王立鹏
张信一
ZHU Yang-ni;ZHANGSUN Yong-gang;GUO He-wei;WANG Li-peng;ZHANG Xin-yi(Northwest Institute of Nuclear Technology,Xi’an 710024,China;State Key Laboratory of Intense Pulsed Radiation Simulation and Effect,Xi’an 710024,China)
出处
《现代应用物理》
2020年第4期36-42,共7页
Modern Applied Physics
关键词
低放射性233
U
热堆
钍铀转化
西安脉冲堆
辐照工艺
low radiation 233 U
thermal reactor
232 Th-233 U conversion
Xi’an Pulse Reactor
irradiation process
