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针对快堆物理特点,提出一套用于快堆堆芯核设计和稳态分析的计算程序NECP-SARAX1.0。程序采用基于ENDF/BVII的连续能量数据库,利用OPENMC程序产生多群截面,堆芯计算采用非结构网格进行几何建模,采用SN节块输运方法以同时满足临界和次临界堆芯的计算需求,采用微扰方法计算堆芯多普勒系数。数值验证表明,该程序具有较高的计算精度,与蒙特卡洛(MCNP)直接计算相比,有效增殖系数(keff)偏差在100×10-5左右。
According to the physical characteristics of fast reactor, a set of calculation program NECP-SARAX1.0 for reactor core design and steady state analysis is proposed. The program uses a continuous energy database based on ENDF / BVII, uses OPENMC program to generate multi-group cross-sections, the core calculation adopts unstructured grid for geometric modeling, and the SN nodal transport method is used to satisfy both the critical and sub-critical core calculations Demand, use the perturbation method to calculate the core Doppler coefficient. The numerical results show that this program has high computational accuracy, and the effective multiplication coefficient (keff) deviation is about 100 × 10-5 compared with the direct calculation by Monte Carlo (MCNP).