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Physics-oriented optimization strategy for the energy lookup algorithm in continuous energy Monte Carlo neutron transport simulation

机译:连续能量蒙特卡罗中子运输模拟中的能量查找算法的物理化优化策略

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摘要

The continuous energy Monte Carlo method is a most high-fidelity and high-resolution method for neutron transport simulations in reactor physics with minimal approximations. However, one of the major disadvantages is that it is very time-consuming and computational-intensive for large scale whole core simulations, especially for coupling with depletion analysis for realistic reactors. Some recent researches indicate that one of the principle performance bottlenecks for the problem lies in the energy lookup algorithm during the calculation of energy-dependent material cross sections. Therefore, two physics-oriented optimization strategies, based on making use of the physical characteristics of neutron transport behaviors, are developed to optimize the run-time performance of the algorithm for accelerating the energy lookup without any loss in precision and accuracy. The first optimization strategy is called Neighbored Material Cascade Grid (NMCG) which is a hybrid approach utilizing the key features of the cascade grid and double indexing method. The second optimization strategy is called Adaptive Optimal Logarithmic Grid (AOLG) which is a variation of the conventional logarithmic energy grid method utilizing the advantages of energy hash tables. The strategies are incorporated into a continuous energy Monte Carlo neutron transport code and tested on realistic whole-core reactor systems. The computational performance as measured by memory usage, elapsed runtime and overall speedup, associated with each of the optimization strategies are demonstrated in the whole-core Monte Carlo simulations. Depending on the complexity of the models, the number of nuclides in the material compositions and the utilization of different optimization strategies, overall speedup ratios of 1.2-1.7, relative to the conventional binary lookup algorithm, are routinely observed. Furthermore, the numerical results indicate that the runtime performance of the new physics-oriented optimization st
机译:连续能量蒙特卡罗方法是最高保真和高分辨率,具有最小近似值的反应器物理中的中子传输模拟。然而,其中一个主要缺点是,对于大规模的整体核心模拟是非常耗时和计算密集的,特别是对于与现实反应器的耗尽分析耦合。一些最近的研究表明,问题的原理性能瓶颈之一是在计算能量相关材料横截面期间的能量查找算法。因此,开发了两种物理化优化策略,基于利用中子传输行为的物理特性,以优化算法的运行时间性能,以加速能量查找,无需精确和精度。第一优化策略称为邻近材料级联网格(NMCG),其是利用级联网格的关键特征和双索引方法的混合方法。第二优化策略称为自适应最佳对数网格(AOLG),其是利用能量哈希表的优点的传统对数能网格方法的变化。该策略纳入连续能量蒙特卡罗中子传输代码,并在现实的全核反应堆系统上进行测试。通过内存使用量,经过的运行时和整体加速度,与每个优化策略相关联的计算性能在全核蒙特卡罗模拟中展示了与每个优化策略相关联。根据模型的复杂性,常规地观察到与传统二进制查找算法的材料组合物中的核素数量和不同优化策略的利用率,1.2-1.7的整体加速比。此外,数值结果表明,新物理化优化ST的运行时性能

著录项

  • 来源
    《Computer physics communications》 |2019年第2019期|共13页
  • 作者单位

    Univ South China Sch Nucl Sci &

    Technol Hengyang 421001 Hunan Peoples R China;

    Univ South China Sch Nucl Sci &

    Technol Hengyang 421001 Hunan Peoples R China;

    Univ South China Sch Environm &

    Safety Engn Hengyang 421001 Hunan Peoples R China;

    Univ South China Sch Nucl Sci &

    Technol Hengyang 421001 Hunan Peoples R China;

    Univ South China Sch Nucl Sci &

    Technol Hengyang 421001 Hunan Peoples R China;

    Univ South China Sch Nucl Sci &

    Technol Hengyang 421001 Hunan Peoples R China;

    Univ South China Sch Environm &

    Safety Engn Hengyang 421001 Hunan Peoples R China;

    Univ South China Sch Nucl Sci &

    Technol Hengyang 421001 Hunan Peoples R China;

    Univ South China Sch Nucl Sci &

    Technol Hengyang 421001 Hunan Peoples R China;

  • 收录信息
  • 原文格式 PDF
  • 正文语种 eng
  • 中图分类 计算机的应用;
  • 关键词

    Continuous energy; Monte Carlo; Neutron transport; Energy lookup; Optimization;

    机译:连续能量;蒙特卡罗;中子运输;能量查找;优化;

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