基于热堆的钍铀转换过程中^(232)U生成的模拟计算  

Simulative calculation of ^(232)U productions in thorium-uranium transform process based on thermal reactor

作　　者：熊文纲[1,2] 李文新[1] 王敏[1] 

机构地区：[1]中国科学院上海应用物理研究所,上海201800 [2]中国科学院研究生院,北京100049

出　　处：《核技术》2012年第5期395-400,共6页Nuclear Techniques

摘　　要：在钍铀燃料循环过程中生成的232U的衰变子体具有强放射性,对燃料循环具有重要影响。本工作采用ORIGEN2、SCALE5程序,以及基于Bateman方法编写的程序,分析了在不同条件下,热堆中钍反应生成232U的规律。一般情况下,232U主要由232Th的(n,2n)反应链生成,而在中子能谱更软情况下,230Th对232U生成贡献增大;CANDU型重水堆和压水堆的含钍燃料组件的燃耗计算结果表明,铀中232U含量随燃耗深度增加而变大,同时初始230Th/Thtotal大小直接线性影响卸料燃耗时232U/Utotal或232U/233U。The decay products of 232U produced in the thorium-uranium fuel cycle emit high energy γ-rays.This affects the fuel cycle greatly.In this paper,the 232U productions in thermal reactor using thorium fuel are analyzed by ORIGEN2,SCALE5 and the code based on the Bateman method.Under normal situation,232U is mainly produced by 232Th（n,2n） reaction chain,and more quantity of 230Th can be transformed into 232U while the neutron spectrum is softer.The burnup calculation of CANDU reactor and PWR assembly indicates that the232U in uranium increase with the burnup,and230Th in fresh thorium has linear correlation with232U/Utotalor232U/233U at discharge burnup.

关 键 词：钍铀燃料循环 232U 230Th 中子能谱 熔盐堆 

分 类 号：TL249[核科学技术—核燃料循环与材料]