SCWR堆芯三维稳态性能分析程序系统开发及验证  

Development and Verification of Three Dimensional Code System for SCWR Core Steady State Analysis

作　　者：王连杰[1] 赵文博[1] 杨平[1] 马永强[1] 卢迪[1] 孙伟[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》2015年第4期41-44,共4页Nuclear Power Engineering

摘　　要：基于节块法中子扩散计算程序,二次开发了具备调棒临界-燃耗计算及燃料管理能力的超临界水堆(SCWR)堆芯稳态中子学计算程序NGFMN_S。通过模块化方式耦合NGFMN_S和超临界水堆子通道热工-水力计算程序ATHAS,开发了超临界水堆堆芯三维物理-热工水力耦合稳态性能分析程序SNTA。针对超临界水堆堆芯CSR1000,通过与耦合程序CASIR及SRAC/SPROD对比检验,结果表明:SNTA程序针对CSR1000问题的计算结果与参考程序符合良好;相比于堆芯计算采用细网有限差分方法的CASIR或SRAC/SPROD程序,SNTA程序的计算效率显著提高;适用于具备强烈核热耦合特性的超临界水堆堆芯的稳态性能分析。A coupled neutronics/thermal-hydraulics three dimensional code system SNTA is developed for SCWR core steady state analysis by modular coupling the improved neutronics nodal method code and SCWR thermal-hydraulic sub-channel code. The problem of CSR1000 core is studied to verify SNTA. The results calculated by SNTA are agreed well with those by CASIR and SRAC. SNTA is more efficient than CASIR and SRAC which neutronics modules are based on the Finite Difference Method. The numeric results show that SNTA can be well applied to SCWR core steady state analysis and core concept design.

关 键 词：超临界水堆 稳态性能分析 物理-热工水力耦合 节块格林函数方法 

分 类 号：TL364[核科学技术—核技术及应用]