Local angular adaptivity CADIS hybrid variance reduction method for monte carlo radiation transport calculations

IF 2.3 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY Annals of Nuclear Energy Pub Date : 2025-03-22 DOI:10.1016/j.anucene.2025.111385

Yufan Zhao , Jingru Han , Jiaxu Zuo , Jiaju Hu , Fudong Liu , Bin Zhang

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Abstract

The Consistent Adjoint Driven Importance Sampling (CADIS) method is a highly effective Monte Carlo (MC) hybrid variance reduction technique; however, its acceleration effects are significantly limited in strongly angular dependent shielding problems involving complex channels. Based on the theory of angular adaptivity, a local angular adaptivity CADIS (LAA-CADIS) hybrid acceleration method is proposed. This method enhances the accuracy of the quadrature set by dynamically adjusting the discrete angular distribution in important regions, thereby better capturing the anisotropic characteristics of angular flux density. The IRI-TUB straight channel benchmark model is selected to validate the acceleration effects of LAA-CADIS. Numerical results indicate that, under the same error conditions, the computational efficiency of LAA-CADIS improves by 34% compared to CADIS. LAA-CADIS accurately describes the neutron importance distribution in strongly angular-dependent shielding models, significantly enhancing Monte Carlo calculation efficiency.

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蒙特卡罗辐射传输计算的局部角适应性 CADIS 混合方差缩小法

一致伴随驱动重要抽样（CADIS）方法是一种高效的蒙特卡罗（MC）混合方差缩减技术；然而，在涉及复杂通道的强角依赖性屏蔽问题中，其加速度效应明显受到限制。基于角自适应理论，提出了一种局部角自适应CADIS （LAA-CADIS）混合加速方法。该方法通过动态调整重要区域的离散角分布来提高正交集的精度，从而更好地捕捉角磁通密度的各向异性特征。选择IRI-TUB直线通道基准模型验证LAA-CADIS的加速度效果。数值结果表明，在相同误差条件下，LAA-CADIS的计算效率比CADIS提高了34%。LAA-CADIS精确地描述了强角依赖性屏蔽模型中的中子重要度分布，显著提高了蒙特卡罗计算效率。

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来源期刊

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.