Transport-corrected flux-moment homogenization method for generating P0 multigroup cross-section based on continuous energy Monte-Carlo

IF 1.9 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Annals of Nuclear Energy Pub Date : 2025-04-23 DOI:10.1016/j.anucene.2025.111448

Yuyang Shen , Yiwei Wu , Qufei Song , Kuaiyuan Feng , Hui Guo , Hanyang Gu

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引用次数: 0

Abstract

The scattering anisotropy multigroup cross-section (MGXS) with respect to the outgoing angle, as well as the anisotropy of the total MGXS with respect to the incident angle, are critical for generating high-precision MGXS used in transport core calculations. A TC-MHT method based on continuous energy Monte-Carlo is developed to generate high-accuracy P₀ MGXS. This method addresses scattering anisotropy using transport correction (TC) and handles the anisotropy of total cross-section through the flux-moment homogenization technique (MHT). This method is validated using the Megapower benchmark. In reactivity calculations, the bias is decomposed and the reasons for the bias are analyzed. The bias is reduced to less than 160 pcm by using the TC-MHT method. For calculations of control drum worth, the bias does not exceed 0.2%. In power calculations, the maximum pin-by-pin power distribution deviation is within 4%. This demonstrates that TC-MHT method can generate high-precision, highly adaptable MGXS for deterministic code.

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基于连续能量蒙特卡罗的P0多群截面的输运校正磁矩均匀化方法

多群截面（MGXS）相对于出射角的散射各向异性，以及总MGXS相对于入射角的各向异性，对于生成用于输运核计算的高精度MGXS至关重要。提出了一种基于连续能量蒙特卡罗的TC-MHT方法来生成高精度的P0 MGXS。该方法利用输运校正（TC）处理散射各向异性，并通过通量矩均匀化技术（MHT）处理总截面的各向异性。使用Megapower基准测试验证了该方法。在反应性计算中，对偏差进行了分解，分析了产生偏差的原因。采用TC-MHT方法将偏置减小到小于160 pcm。对于控制滚筒值的计算，偏差不超过0.2%。在功率计算中，最大引脚间的功率分布偏差在4%以内。这表明TC-MHT方法可以为确定性代码生成高精度、高适应性的MGXS。

本文章由计算机程序翻译，如有差异，请以英文原文为准。

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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.