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三维多群P3 近似MonteCarlo中子输运程序MCMGP3是为反应堆临界安全计算设计的 ,它是从连续点截面中子—光子耦合输运MonteCarlo程序MCNP发展而来 ,程序用多群截面代替了MCNP程序的连续点截面 ,但保留了MCNP程序的几何处理能力 ,计数能力和降低方差技巧及图形功能。能群数可扩展 ,使用宏观截面或微观截面均可 ,中子角分布采用P3 近似和广义Gaussian求积。多个基准问题结果显示 ,MCMGP3程序结果与其它方法计算结果符合很好 ,计算还表明在同样计算精度下 ,MCMGP3程序的计算时间较MCNP程序少得多。此外 ,MCMGP3程序还实现了与WIMS程序的连算 ,可作反应堆全堆数值模拟。
Three-dimensional multi-cluster P3 approximate MonteCarlo neutron transport program MCMGP3 is designed for the critical reactor safety calculation. It is developed from the neutron-photon coupling transport Monte Carlo program MCNP with continuous point cross-section. The program replaces the MCNP program with multi- Of the continuous point cross-section, but retains the geometric processing capabilities of the MCNP program, counting skills and reduce variance techniques and graphics capabilities. The number of energy groups can be expanded, the use of macro-section or micro-section can be used, the distribution of neutron angle using P3 approximation and generalized Gaussian quadrature. The results of multiple benchmark problems show that the results of MCMGP3 are in good agreement with the results of other methods. The calculation also shows that the calculation time of MCMGP3 is much less than that of MCNP under the same computational accuracy. In addition, the MCMGP3 program also achieves the calculation of the WIMS program, which can be used to simulate the entire reactor.