溶液堆燃料管理计算方法初步研究与程序研制  

Development of an In-Core Fuel Management Program for Solution Reactors

作　　者：李云召[1] 吴宏春[1] 曹良志[1] 彭思涛[1] 卢皓亮[1] 宋小明[2] 姚栋[2] 

机构地区：[1]西安交通大学核科学与技术学院,西安710049 [2]中国核动力研究设计院核反应堆系统设计技术国家级重点实验室,成都610041

出　　处：《核动力工程》2009年第6期15-18,23,共5页Nuclear Power Engineering

基　　金：国家自然科学基金资助(10605017;10875094)

摘　　要：溶液型医用同位素生产堆的核燃料呈流动的水溶液形式。堆芯呈非结构、强各向异性散射,运行过程中会产生大量气体。针对堆芯燃料管理计算需要在线提取核素等特点,基于以三角形节块SN方法为模型的中子输运计算程序DNTR,开发了溶液堆堆芯燃料管理计算程序FMSR,并利用该程序对溶液堆进行了模拟分析。结果表明,FMSR程序可在溶液堆堆芯燃料管理计算中试用。Solution reactor, as a new type of medical isotopes production reactor, is with many special features, such as flowing aqueous fissile solution, unstructured geometry, strong anisotropic scattering, and isotopes distillation. They all raise serious challenges for the fuel management calculation of solution reactors. An in-core fuel management calculation program package for solution reactors, called FMSR, is developed based on the DNTR code, a three-dimensional discrete ordinate nodal transport calculation code in triangular meshes. All results calculated by FMSR, including the distribution of power and void and cycle length and coefficients of reactivity, show that the program package can be used for the in-core fuel management calculation of solution reactors as a trial.

关 键 词：溶液堆 燃料管理计算 三角形节块方法SN FMSR 

分 类 号：TL329.3[核科学技术—核技术及应用]