Proposal of Direct Calculation of Kinetic Parameters βeff and Based on Continuous Energy Monte Carlo Method
Proposal of Direct Calculation of Kinetic Parameters βeff and Based on Continuous Energy Monte Carlo Method
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DOI：
10.1080/18811248.2004.9726417
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发表时间：
2005-06
影响因子：
1.2
通讯作者：
Y. Nauchi;T. Kameyama
中科院分区：
文献类型：
--
作者：
Y. Nauchi;T. Kameyama
基于连续能量蒙特卡罗方法，提出了动力学参数的直接计算方法。在所提出的方法中，使用本征值计算来估计有效缓发中子分数βeff和中子产生时间τ。新的裂变中子在下一代的预期数量被应用到所提出的方法，而不是伴随通量，已被传统上使用。建立了估算反应堆堆芯动力学参数的算法，并将其纳入连续能量蒙特卡罗输运计算程序MCNP-4C中，该程序适用于各种中子能谱和几何形状的反应堆堆芯的本征值计算。临界堆芯的βeff和βeff/Emax的计算值与实验值的误差分别为4.5%和10%，验证了所提出方法的有效性。
Direct calculation methods of kinetic parameters are proposed based on the continuous energy Monte Carlo method. In the proposed methods, the effective delayed neutron fraction βeff and the neutron generation time ∧ are estimated using eigenvalue calculations. The expected number of fission neutrons in the next generation is newly applied to the proposed methods instead of the adjoint flux that has been conventionally used. The algorithms to estimate the kinetic parameters are established and incorporated into the continuous energy Monte Carlo transport calculation code MCNP-4C, which is versatile for eigenvalue calculations of nuclear reactor cores with various types of neutron energy spectrum and geometry. The proposed methods were validated since the calculated values agreed with the experimental data of βeff and βeff/∧ for the critical cores within accuracies of 4.5% and 10%, respectively.