堆芯中子学程序系统SARCS-4.0的开发及初步验证  

Development and V&V of Advanced Neutronics Code System SARCS-4.0

作　　者：柴晓明[1] 马永强[1] 王育威[1] 芦韡[1] 姚栋[1] 

机构地区：[1]中国核动力研究设计院核反应堆系统设计技术重点实验室,成都610041

出　　处：《核动力工程》2013年第S1期24-26,共3页Nuclear Power Engineering

摘　　要：开发了堆芯中子学程序系统SARCS-4.0,该程序系统能处理由任意方形燃料组件组成的堆芯;能计算铀钚、钍铀燃料循环;能计算硼、钆、铒、铪、银、铟、铕、钐等各类可燃毒物和含硼、铪、银-铟-铬、铕、镝等各类控制棒;具备堆芯核设计的基本功能。使用SARCS-4.0系统对超临界水冷反应堆(SCWR)堆芯进行计算以验证程序系统的计算准确性,结果表明,SARCS-4.0系统具有较高计算精度,该系统从功能上、精度上均适用于新型反应堆堆芯选型研究。An advanced neutronics code system SARCS-4.0,which can simulate the core composed by arbitrary square assemblies,calculate Uranium-Plutonium and Thorium-Uranium cycle,treat many burnable poisons(such as B,Gd,Er,Hf,Ag,In,Eu,Sm.etc) and several control rod materials,is introduced in this paper.The SCWR reactor core is calculated by SARCS-4.0.The results show that SARCS-4.0 is accurate enough to design the reactor core.

关 键 词：核反应堆 中子学程序 SARCS-4 可燃毒物 超临界水冷反应堆 

分 类 号：TL351.1[核科学技术—核技术及应用]