Development of a MC/MOC two-step method for sodium fast reactor analysis with transport-corrected flux-moment multigroup cross-section generation method

IF 2.3 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Yiwei Wu , Qufei Song , Yuyang Shen , Hui Guo , Yao Xiao , Hanyang Gu
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引用次数: 0

Abstract

New fast reactor designs could feature complex geometries and axial heterogeneity. The MC/MOC two-step method has the advantage of the high adaptability of Monte Carlo (MC) and Method of Characteristics (MOC) to geometry, offering a precise solution for such reactors. However, limited studies exist on applying the MOC method to 3D sodium fast reactors. MC-generated multi-group cross-sections, which ignore the anisotropy with respect to neutron direction, introduce bias in transport calculations. This paper develops a two-step MC/MOC approach, integrating the direct 3D MOC method and the Transport-corrected flux-moment homogenization technique (TC-MHT) for 3D reactor problems. The scheme is verified on the sodium-cooled fast reactor MET-1000, the results confirm the feasibility of the method for both homogeneous and heterogeneous core geometries. The TC-MHT method significantly reduces calculation bias, with eigenvalue bias below 200 pcm, heterogeneous pin power bias under 3.1%, and homogeneous assembly power bias under 1.4%.
基于输运修正通量矩多群截面生成法的钠快堆MC/MOC两步法研究
新的快堆设计可能具有复杂的几何形状和轴向非均质性。MC/MOC两步法具有蒙特卡罗(MC)和特征法(MOC)对几何形状高度适应的优点,为该类反应器提供了精确的求解方法。然而,将MOC方法应用于三维钠快堆的研究还很有限。mc生成的多群截面忽略了中子方向的各向异性,在输运计算中引入了偏差。本文提出了一种两步MC/MOC方法,将直接3D MOC方法和输运校正的通量矩均匀化技术(TC-MHT)相结合,用于三维反应器问题。在钠冷快堆MET-1000上进行了验证,结果证实了该方法在均质和非均质堆芯几何形状上的可行性。TC-MHT方法显著降低了计算偏差,特征值偏差在200 pcm以下,异质引脚功率偏差在3.1%以下,均匀组装功率偏差在1.4%以下。
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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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