堆芯中子学程序系统SARCS-4.0的开发及初步验证

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

Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China, Chengdu, 610041, China

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。
- 核反应堆 /
- 中子学程序 /
- SARCS-4 /
- 可燃毒物 /
- 超临界水冷反应堆
Abstract: 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.
- Nuclear reactor /
- Neutronics code /
- SARCS-4 /
- Burnable poison /
- SCWR