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首页> 外文期刊>Life Cycle Reliability and Safety Engineering >Use of finite-difference diffusion Monte Carlo method to generate Shannon entropy of the fission distribution in a nuclear reactor core
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Use of finite-difference diffusion Monte Carlo method to generate Shannon entropy of the fission distribution in a nuclear reactor core

机译：使用有限差分扩散蒙特卡洛方法来生成香农熵的裂变分布在核反应堆核心

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摘要

Monte Carlo criticality calculation is an iterative process which requires a guess fission distribution to start the simulations. It is important to assess when the fission source has converged, so that a sufficient number of the initial batches are discarded prior to beginning of the Monte Carlo (MC) tallies. Shannon entropy has been highly effective in characterizing convergence of the fission distribution in a reactor core. To compute Shannon entropy, transport-based MC code usually requires additional binning of the geometry along with the use of algorithms to get the distribution of fission source in these bins. This binning is done by superimposing a grid kind of structure over and above the geometry defined for transport simulation. The entropy computation in transport-based MC code thus involves additional computational efforts. In this paper, we have used finite-difference (FD) difference based diffusion MC method to calculate Shannon entropy. In this method, problem is divided into regular meshes. Shannon entropy is estimated in these mesh structures without any additional computational efforts. Shannon entropy for 3D PHWR benchmark is estimated by this method and is compared with Transport MC Code PATMOC and 3D Space Time Kinetics Code KINFIN and the results are found to be in good agreement.
机译：蒙特卡罗是一个临界计算迭代过程中需要猜裂变分布开始模拟。重要的评估当裂变源聚合,这足够数量的初始批量开始之前被丢弃蒙特卡罗(MC)的记录。一直在高度有效的描述裂变分布的收敛性反应堆堆芯。transport-based MC代码通常需要额外的几何和装箱使用的算法得到的分布在这些箱子裂变源。通过网格叠加的结构超过的几何定义运输模拟。因此需要额外transport-based MC代码计算工作。使用基于有限差分(FD)的区别扩散MC方法计算夏侬熵。在这种方法中,分为常规问题网格。没有任何额外的网状结构计算工作。PHWR基准是由这种方法和估计与运输MC代码PATMOC和3 d时空动力学代码KINFIN和结果发现是在良好的协议。

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