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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。
Based on the nodule diffusion neutron diffusion calculation program, the nuclear steady-state neutronics calculation program NGFMN_S of the supercritical water reactor (SCWR) with criticality-burnup calculation and fuel management capability of the wand is developed. Through the modular coupling of NGFMN_S and ATHAS, a thermal-hydromechanical calculation program for sub-channel of supercritical water reactor, SNTA was developed for three-dimensional physical-thermal-hydraulic coupling steady-state performance analysis of supercritical water reactor core. The results show that the calculation results of SNTA program against CSR1000 are in good agreement with the reference program by comparing with CASIR and SRAC / SPROD of supercritical water reactor core. Compared with the core calculation, the finite difference method of fine mesh CASIR or SRAC / SPROD program, the computational efficiency of SNTA program is significantly improved. It is suitable for steady state performance analysis of supercritical water reactor core with strong thermal-thermal coupling characteristics.