基于COME的四面体非结构网格中子输运并行计算方法研究

Research on Parallel Computing Method for Neutron Transport on Tetrahedral Unstructured Meshes Based on COME

  • 摘要: 异形复杂几何核反应堆堆芯的精细化中子输运求解一直是核反应堆物理计算的热点和难点,而非结构网格并行求解方法由于其优异的几何适应性,广泛应用于异形复杂几何堆芯的大规模数值模拟研究。本文基于华中科技大学虚拟反应堆耦合分析实验室开发的COME耦合平台,开发了四面体非结构网格的三维多群并行中子输运求解程序TETRIS,TETRIS程序角度离散采用离散纵标法,空间离散采用间断有限元。由于异形复杂几何核反应堆堆芯材料分布不均匀,传统源迭代求解中子输运方程难度高,为加速中子输运方程的求解效率,TETRIS程序基于Matrix-Free方法在COME平台上实现Krylov子空间加速方法。此外,由于精细化刻画核反应堆需要大量的非结构网格,内存需求大且计算时间长,为减少计算时间与内存需求,TETRIS程序对空间变量实现基于MPI的block-Jacobi空间并行扫描方案,对能群实现基于MPI的并行求解,对角度方向实现基于OpenMP的并行求解。针对PinCell模型、六边形几何模型、C5G7基准模型以及KNK-Ⅱ实验快中子反应堆模型的计算结果表明:TETRIS程序具有良好的计算精度、并行效率和几何适用性,与多群蒙特卡罗的计算精度相当。与多群OpenMC蒙特卡罗参考结果相比,4个算例的有效增殖因数偏差低于100 pcm,功率相对偏差低于1.4%。不同并行策略计算消耗统计结果表明,TETRIS程序百核并行效率绝大部分在50%以上,Krylov子空间方法加速比最高为3.47。

     

    Abstract: High-fidelity neutron transport solutions for irregular and complex reactor cores remain a key challenge and focal point in reactor physics calculations. Traditional deterministic programs are incapable of finely resolving reactors with complex and non-standard geometries. Leveraging their superior geometric adaptability, parallel unstructured mesh solution methods are widely applied for large-scale numerical simulations of complex reactor core geometries. A three-dimensional multi-group parallel neutron transport solver on tetrahedral unstructured meshes developed on the COME coupling platform by the Virtual Reactor Coupling Analysis Laboratory at Huazhong University of Science and Technology, was presented in this study. TETRIS utilizes discrete ordinates method for angular discretization and discontinuous finite elements method for spatial discretization. Owing to the inhomogeneous distribution of materials in complex geometric reactor cores, traditional source iteration methods face significant challenges in solving neutron transport equations efficiently. To accelerate neutron transport calculations and reduce the difficulty of solving the transport equation, the TETRIS was implemented a Krylov subspace acceleration method based on a matrix-free approach on the COME platform. Moreover, due to the extensive use of unstructured meshes required for detailed modeling of nuclear reactors, which demands substantial memory and prolongs computation time, the TETRIS was implemented a parallel sweeping scheme using MPI for spatial variables, alongside MPI-based parallel resolution for energy groups, and OpenMP for angular directions to reduce both computational time and memory requirements significantly, the parallel sweeping scheme employs a pipeline sweeping algorithm, while the multi-region parallel sweeping models utilizes a block-Jacobi parallel strategy. The computational results for the PinCell model, hexagonal assembly model, C5G7 benchmark model, and KNK-Ⅱ experimental fast neutron reactor model show that TETRIS exhibits commendable computational accuracy, parallel efficiency and geometric applicability, achieving numerical accuracy comparable to that of multi-group Monte Carlo methods. For the PinCell model, the deviation in keff is 61 pcm, while the hexagonal geometry model shows a deviation of 86 pcm. For the KNK model under two conditions, the maximum deviation in keff is 39 pcm, with the maximum relative deviation in power distribution being 0.242%. In the C5G7 2D model, the deviation in keff is 13 pcm, and the maximum relative deviation in power distribution is 1.4%. In summary, the effective multiplication factor deviations for all four test cases are within 100 pcm, with relative power error below 1.4%. The computational time for different parallel strategies indicates that the TETRIS achieves parallel efficiency of over 50% in most cases when utilizing over 100 cores. The acceleration factor achieved by the Krylov subspace method reaches a maximum of 3.47.

     

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