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作 者:马进[1] 刘志宾[1,2] 王兵树[1] MA Jin;LIU Zhi-bin;WANG Bing-shu(Department of Automation North China Electric Power University,Baoding,071003,China;China Techenergy Co.,LTD,Beijing,100094,China)
机构地区:[1]华北电力大学自动化系,河北保定071003 [2]北京广利核系统工程有限公司,北京100094
出 处:《核科学与工程》2018年第4期577-584,共8页Nuclear Science and Engineering
摘 要:利用幂法和SOR非线性迭代法求解两群中子扩散方程。在CANDU堆的数值计算结果表明:本方法比内循环采用SOR、外循环采用Wielandt结合源外推法在运行速率和迭代次数上要更好;同时迭代过程也印证了SOR的松弛因子对运行时间和迭代次数有着比较大的影响,松弛因子的选择能有效降低迭代次数并提高运行效率。通过与参考数据比较得出keff误差为0.38%,全堆芯390个通道的满功率与热工水力计算的值误差为-0.16%,功率分布在堆芯内部误差0.6%以内,外部偏差为1%~2%,说明了本模型具有比较高的计算精度,可以作为核电仿真机的CANDU堆芯计算算法。Using power method and SOR nonlinear iteration to solve the two group neutron diffusion equation.The results of iterative process in CANDU reactors is compared with the inner iteration using SOR method and outer iteration using Wielandt combined source extrapolation method,the results of power method and SOR is better than the latter on CPU running time and the number of iterations.The iterative process also confirms that the relaxation factor of SOR has a relatively large impact on the running time and the number of iterations.Reasonable selection of SOR relaxation factor will effectively reduce the number of iterations and improve operational efficiency.The keff deviation is 0.38%,the deviation of 390 channels of the calculated value separately with the thermal hydraulic force is-0.16%.The deviation of power distributed in each channel within the core is less than 0.6%,the external deviation of 1%to 2%,indicating that the model has a relatively high accuracy,which can be used as a core neutron physics calculation tool for CANDU reactor simulator.
分 类 号:TP391.9[自动化与计算机技术—计算机应用技术]
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