{"title":"P1 generalized equivalence theory for PWR-core pin-by-pin neutronics calculation","authors":"Junwei Qin, Yunzhao Li, Liangzhi Cao, Hongchun Wu","doi":"10.1016/j.anucene.2024.111147","DOIUrl":null,"url":null,"abstract":"<div><div>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 P<sub>3</sub> (SP<sub>3</sub>) theory. To further reduce computational cost, this work proposes a two-step approach based on P<sub>1</sub> theory. This work presents several key advancements in achieving efficient and accurate neutronics calculations. First, the P<sub>1</sub> 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 P<sub>1</sub> 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 SP<sub>3</sub>-level accuracy with computing cost comparable to neutron diffusion.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"213 ","pages":"Article 111147"},"PeriodicalIF":1.9000,"publicationDate":"2024-12-26","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":null,"platform":"Semanticscholar","paperid":null,"PeriodicalName":"Annals of Nuclear Energy","FirstCategoryId":"5","ListUrlMain":"https://www.sciencedirect.com/science/article/pii/S0306454924008107","RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"Q1","JCRName":"NUCLEAR SCIENCE & TECHNOLOGY","Score":null,"Total":0}
引用次数: 0
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.
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.