P1 generalized equivalence theory for PWR-core pin-by-pin neutronics calculation

IF 2.3 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY Annals of Nuclear Energy Pub Date : 2025-04-01 Epub Date: 2024-12-26 DOI:10.1016/j.anucene.2024.111147
Junwei Qin, Yunzhao Li, Liangzhi Cao, Hongchun Wu
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Abstract

The essence of steady-state neutronics analysis for a nuclear reactor core lies in solving the six-dimensional the Boltzmann neutron transport linear equation. Due to the expensive computational cost in direct solving schemes, the two-step procedure based on homogenization theory has been the workhorse for decades for core neutronics calculation. Among these methods, the pin-by-pin two-step procedure has recently emerged as the most attractive option. The current widely-used pin-by-pin two-step procedure is based on the Simplified P3 (SP3) theory. To further reduce computational cost, this work proposes a two-step approach based on P1 theory. This work presents several key advancements in achieving efficient and accurate neutronics calculations. First, the P1 equation is derived from the Boltzmann neutron transport equation through a first-order spherical harmonic expansion of the angular flux in the angle-space. It comprises the angular-dependent total cross-sections and the first-order anisotropic scattering cross-sections, thereby eliminating the approximation introduced by the traditional Fick’s Law. Second, a Generalized Equivalent Theory (GET) approach is established to generate the Pin-cell Discontinuity Factors (PDF), ensuring the conservations of key quantities during homogenization. Lastly, the pin-cell homogenized cross-sections and PDF can be used to solve the P1 equation numerically. This work employs the Finite Difference Method (FDM) for spatial discretization. The proposed method and code implementation have been verified via a series of validation tests. The results demonstrate that this new methodology achieves the SP3-level accuracy with computing cost comparable to neutron diffusion.
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P1广义等效理论用于pwr堆芯逐脚中子计算
核反应堆堆芯稳态中子分析的实质在于求解六维玻尔兹曼中子输运线性方程。由于直接求解方案的计算成本昂贵,基于均质化理论的两步法几十年来一直是核心中子计算的主要方法。在这些方法中,针接针的两步手术最近成为最具吸引力的选择。目前广泛使用的针接针两步程序是基于简化的P3 (SP3)理论。为了进一步降低计算成本,本工作提出了一种基于P1理论的两步法。这项工作提出了实现高效和准确的中子计算的几个关键进展。首先,通过角空间中角通量的一阶球谐展开,从玻尔兹曼中子输运方程推导出P1方程。它包括角相关的总截面和一阶各向异性散射截面,从而消除了传统菲克定律引入的近似。其次,建立了一种广义等效理论(GET)方法来生成Pin-cell不连续因子(PDF),保证了均匀化过程中关键量的守恒性。最后,pin-cell均质截面和PDF可以用于数值求解P1方程。本文采用有限差分法(FDM)进行空间离散化。所提出的方法和代码实现已通过一系列验证测试进行了验证。结果表明,该方法达到了sp3级的精度,计算成本与中子扩散相当。
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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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