Minh-Hieu Do, Karim Ammar, Nicolas Gerard Castaing, François Madiot
{"title":"具有非均匀系数的中子扩散方程的混合对偶形式的物理信息神经网络","authors":"Minh-Hieu Do, Karim Ammar, Nicolas Gerard Castaing, François Madiot","doi":"10.1016/j.anucene.2025.111607","DOIUrl":null,"url":null,"abstract":"<div><div>Physics-Informed Neural Networks (PINNs), a popular deep learning framework for numerical approximations of Partial Differential Equations (PDEs), are investigated in this work to approximate the solution of the neutron diffusion equation, which is used in simulations of nuclear reactor cores. Moreover, this equation may have low regularity solution due to heterogeneous coefficients, which presents a challenge for the PINNs approach based on the primal form of the neutron diffusion equation. In this work, we study the PINNs approach for the mixed dual form of the neutron diffusion equation and aim to demonstrate that it can significantly improve the accuracy of the approximate solution, especially in cases with heterogeneous coefficients, compared to the primal approach. Besides, neural networks are typically based on the inverse power method for the k-eigenvalue problem, and it is well-known that this algorithm converges very slowly if the dominance ratio is high, as is commonly the case in several reactor physics applications. Therefore, we also discuss some acceleration methods for the PINNs approach applied to the k-eigenvalue problem. Several numerical test cases for the source and k-eigenvalue problems illustrate our purposes.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"223 ","pages":"Article 111607"},"PeriodicalIF":1.9000,"publicationDate":"2025-06-19","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":"{\"title\":\"Physics Informed Neural Networks for the mixed dual form of the neutron diffusion equation with heterogeneous coefficients\",\"authors\":\"Minh-Hieu Do, Karim Ammar, Nicolas Gerard Castaing, François Madiot\",\"doi\":\"10.1016/j.anucene.2025.111607\",\"DOIUrl\":null,\"url\":null,\"abstract\":\"<div><div>Physics-Informed Neural Networks (PINNs), a popular deep learning framework for numerical approximations of Partial Differential Equations (PDEs), are investigated in this work to approximate the solution of the neutron diffusion equation, which is used in simulations of nuclear reactor cores. Moreover, this equation may have low regularity solution due to heterogeneous coefficients, which presents a challenge for the PINNs approach based on the primal form of the neutron diffusion equation. In this work, we study the PINNs approach for the mixed dual form of the neutron diffusion equation and aim to demonstrate that it can significantly improve the accuracy of the approximate solution, especially in cases with heterogeneous coefficients, compared to the primal approach. Besides, neural networks are typically based on the inverse power method for the k-eigenvalue problem, and it is well-known that this algorithm converges very slowly if the dominance ratio is high, as is commonly the case in several reactor physics applications. Therefore, we also discuss some acceleration methods for the PINNs approach applied to the k-eigenvalue problem. Several numerical test cases for the source and k-eigenvalue problems illustrate our purposes.</div></div>\",\"PeriodicalId\":8006,\"journal\":{\"name\":\"Annals of Nuclear Energy\",\"volume\":\"223 \",\"pages\":\"Article 111607\"},\"PeriodicalIF\":1.9000,\"publicationDate\":\"2025-06-19\",\"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/S0306454925004244\",\"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}","platform":"Semanticscholar","paperid":null,"PeriodicalName":"Annals of Nuclear Energy","FirstCategoryId":"5","ListUrlMain":"https://www.sciencedirect.com/science/article/pii/S0306454925004244","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}
Physics Informed Neural Networks for the mixed dual form of the neutron diffusion equation with heterogeneous coefficients
Physics-Informed Neural Networks (PINNs), a popular deep learning framework for numerical approximations of Partial Differential Equations (PDEs), are investigated in this work to approximate the solution of the neutron diffusion equation, which is used in simulations of nuclear reactor cores. Moreover, this equation may have low regularity solution due to heterogeneous coefficients, which presents a challenge for the PINNs approach based on the primal form of the neutron diffusion equation. In this work, we study the PINNs approach for the mixed dual form of the neutron diffusion equation and aim to demonstrate that it can significantly improve the accuracy of the approximate solution, especially in cases with heterogeneous coefficients, compared to the primal approach. Besides, neural networks are typically based on the inverse power method for the k-eigenvalue problem, and it is well-known that this algorithm converges very slowly if the dominance ratio is high, as is commonly the case in several reactor physics applications. Therefore, we also discuss some acceleration methods for the PINNs approach applied to the k-eigenvalue problem. Several numerical test cases for the source and k-eigenvalue problems illustrate our purposes.
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.