使用蒙特卡罗方法计算均匀化群常数时,一般以中子标通量为权重计算平均散射角余弦,会引入额外的计算误差.针对该问题,本文从中子均方位移和平均散射角余弦的关系出发,根据中子均方位移的统计结果,计算得到保证该物理量守恒的平均散射角余弦.基于蒙特卡罗粒子输运计算程序NECP-MCX,并使用各向异性较强的快中子反应堆问题对该方法进行了测试.相比于传统方法,反应堆有效增殖因子的偏差由 588×10-5~796×10-5 降低为-31×10-5~266×10-5,相对裂变反应率分布的最大相对偏差由 3.754%~4.675%降低为-0.990%~0.920%,均方根偏差由 1.864%~2.444%降低为 0.569%~0.612%.结果表明:本文方法可以可以有效降低传统方法的计算偏差,具有一定的应用价值.
In the two-step calculation of reactor physics,the average scattering cosine is determined using the scalar flux as the weighting function in the Monte Carlo method for generating group constants,which introduces additional errors.Therefore,starting from the relationship between the mean square displacement and average scattering co-sine,this paper proposes a novel method that calculates the average scattering cosine,conserving the mean square displacement of neutrons.It is realized based on the Monte Carlo particle transport procedure NECP-MCX.Several fast reactor problems with strong anisotropy are selected to test the validity of the proposed method.Compared with the traditional method,the biases of multiplication factors decrease from 588×10-5~796×10-5 to-31×10-5~266×10-5.The maximum relative biases of relative fission reaction rates decrease from 3.754%~4.675%to-0.990%~0.920%,and the root mean squared biases decrease from 1.864%~2.444%to 0.569%~0.612%.The results show that the proposed method can effectively reduce the biases introduced by the traditional method,and has cer-tain application values.