Coarse mesh finite difference acceleration of the random ray method

IF 1.9 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY Annals of Nuclear Energy Pub Date : 2024-08-21 DOI:10.1016/j.anucene.2024.110848
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Abstract

This paper presents the development and evaluation of the Coarse Mesh Finite Difference (CMFD) acceleration method to The Random Ray Method (TRRM). We demonstrate its effectiveness in accelerating the convergence of the fission sources and reducing the real statistical error in neutron transport calculations. TRRM treats the angular variable of the neutron flux stochastically and performs batch sampling of characteristic rays to transform the Method of Characteristics (MOC) into a stochastic process, that is capable of making significant strides in memory efficiency and computational performance for some problems. Despite its advantages, TRRM exhibits a potential challenge with a large number of inactive cycles and inherent inter-cycle correlation much like the Monte Carlo method. To address this, the CMFD acceleration method is explored and demonstrated to dramatically reduce the number of required inactive cycles and diminish inter-cycle correlation. Results from the numerical analysis of a 2D C5G7 core problem indicate that the application of CMFD leads to enhanced convergence, with the integration of a CMFD acceleration step every cycle offering the most substantial reduction in statistical noise and error. The study reveals that applying CMFD with every cycle effectively resolves the issue of needing inactive cycles and significantly lowers the inter-cycle correlation, thereby providing a more accurate estimation of standard deviation for pin power distributions. We conclude that using CMFD not only minimizes the number of inactive cycles of TRRM – much like normal Monte Carlo transport – but also lowers real statistical error effectively. For a targeted maximum standard deviation of 0.1% in the pin power, the addition of CMFD can decrease the number of necessary active cycles by 41% compared to standard TRRM, as demonstrated by the 2D C5G7 benchmark analysis.

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粗网格有限差分加速随机射线法
本文介绍了随机射线法(TRRM)的粗网格有限差分(CMFD)加速方法的开发和评估。我们展示了该方法在加速裂变源收敛和减少中子输运计算实际统计误差方面的有效性。TRRM 随机处理中子通量的角度变量,并对特征射线进行批量采样,将特征法(MOC)转化为随机过程,能够在内存效率和某些问题的计算性能方面取得显著进步。尽管 TRRM 具有诸多优势,但它也面临着潜在的挑战,即大量的非活动周期和周期间固有的相关性与蒙特卡罗方法非常相似。为解决这一问题,我们探索并演示了 CMFD 加速方法,以显著减少所需的非活动周期数量并降低周期间相关性。对二维 C5G7 核心问题的数值分析结果表明,CMFD 的应用提高了收敛性,每个周期集成一个 CMFD 加速步骤可最大幅度地减少统计噪声和误差。研究表明,在每个周期应用 CMFD 可以有效解决需要非活动周期的问题,并显著降低周期间相关性,从而更准确地估计引脚功率分布的标准偏差。我们的结论是,使用 CMFD 不仅能最大限度地减少 TRRM 的非活动循环次数(与正常的蒙特卡罗传输类似),还能有效降低实际统计误差。对于引脚功率中 0.1% 的目标最大标准偏差,与标准 TRRM 相比,增加 CMFD 可以将必要的活动循环次数减少 41%,这一点已在 2D C5G7 基准分析中得到证明。
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来源期刊
Annals of Nuclear Energy
Annals of Nuclear Energy 工程技术-核科学技术
CiteScore
4.30
自引率
21.10%
发文量
632
审稿时长
7.3 months
期刊介绍: Annals of Nuclear Energy provides an international medium for the communication of original research, ideas and developments in all areas of the field of nuclear energy science and technology. Its scope embraces nuclear fuel reserves, fuel cycles and cost, materials, processing, system and component technology (fission only), design and optimization, direct conversion of nuclear energy sources, environmental control, reactor physics, heat transfer and fluid dynamics, structural analysis, fuel management, future developments, nuclear fuel and safety, nuclear aerosol, neutron physics, computer technology (both software and hardware), risk assessment, radioactive waste disposal and reactor thermal hydraulics. Papers submitted to Annals need to demonstrate a clear link to nuclear power generation/nuclear engineering. Papers which deal with pure nuclear physics, pure health physics, imaging, or attenuation and shielding properties of concretes and various geological materials are not within the scope of the journal. Also, papers that deal with policy or economics are not within the scope of the journal.
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