Monte Carlo Fission Matrix Acceleration Method with Limited Inner Iteration

Pan, Liujun; Wang, Ruihong; Jiang, Song

doi:10.13182/nse14-73

Cited by 10 publications

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“…如果在 Monte Carlo 模拟中使用代裂变矩阵的主特征向量 S (n) fm 对裂变源分布进行校正, 当 Monte Carlo 计数得到的 S (n) mc 接近真实分布 (裂变源分布接近收敛) 时, 统计误差有可能使得 S (n) fm 与 S (n) mc 差异较大, 这种校正反而使得裂变源分布远离真实分布. 内迭代限制的裂变矩阵加速方法 (FM-Lii) [17] 通过寻找新的向量校正裂变源分布来缓解这种不稳定性. [18,19] .…”

Section: 内迭代限制unclassified

Review of convergence acceleration methods in Monte Carlo criticality calculations for reactor analysis

et al. 2016

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The core problem of criticality calculations in nuclear analysis is to calculate the fission source distributions of systems. As the computing performance of hardware and software has advanced, Monte Carlo methods have been applied to the nuclear analysis of whole core problems, because the accuracy of the Monte Carlo calculations has been enhanced by its ability to use continuous energy nuclear data and to handle complex geometry information. When approaching whole core analyses, the Monte Carlo criticality calculations must handle some challenging problems, such as slow convergence, the stopping criteria of source convergence, and real variance estimations. Here, the theory and challenges of Monte Carlo criticality are introduced, and progress in convergence acceleration methods and variance reduction techniques is reviewed.

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Section: 内迭代限制unclassified

Review of convergence acceleration methods in Monte Carlo criticality calculations for reactor analysis

et al. 2016

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“…Several deterministic techniques have been applied to accelerate Monte Carlo source convergence, by reducing the number of inactive cycles used to converge the fission source: e.g., fission matrixbased methods (Kitada and Takeda [1], Carney et al [2], Pan et al [3], Dufek and Tuttelberg [4]), Wielandt-based methods (Yamamoto and Miyoshi [5], She et al [6]), hybrid CMFD/Monte Carlo method (Lee et al [7]), response matrix-based method (Leppänen [8]).…”

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confidence: 99%

Enhancing the Performance of Fission Source Convergence With Functional Expansion Tallies in Serpent 2 Monte Carlo Code

2021

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This paper presents an upgrade to the built-in response matrix based solver implemented in Serpent 2 Monte Carlo code aiming to improve the fission source convergence when obtaining the forward solution to the k-eigenvalue criticality source problems. The functional expansion tallies are introduced in an attempt to improve the accuracy of the cell-wise form factors that feed the response matrix solver, replacing the current mesh-based approach. The functional expansion tallies reconstruct the binning surface and collision tallies, by using high-order series expansion to represent the original and continuous spatial distributions. This new feature is implemented to Serpent 2 and tested by single-assembly and full-core PWR calculations (BEAVRS benchmark). The results show enhanced performance of the convergence acceleration methodology based on an improved initial guess of the fission source.

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Correlation of errors in the Monte Carlo fission source and the fission matrix fundamental-mode eigenvector

Dufek

Holst

2016

Annals of Nuclear Energy

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Monte Carlo Fission Matrix Acceleration Method with Limited Inner Iteration

Cited by 10 publications

References 0 publications

Review of convergence acceleration methods in Monte Carlo criticality calculations for reactor analysis

Review of convergence acceleration methods in Monte Carlo criticality calculations for reactor analysis

Enhancing the Performance of Fission Source Convergence With Functional Expansion Tallies in Serpent 2 Monte Carlo Code

Correlation of errors in the Monte Carlo fission source and the fission matrix fundamental-mode eigenvector

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