Artur Souza e Silva, Alessandro da Cruz Gonçalves, Willian Vieira de Abreu, Adilson Costa da Silva, Aquilino Senra Martinez
{"title":"利用高斯过程回归重建堆芯内探测器测量的功率分布","authors":"Artur Souza e Silva, Alessandro da Cruz Gonçalves, Willian Vieira de Abreu, Adilson Costa da Silva, Aquilino Senra Martinez","doi":"10.1016/j.anucene.2025.111581","DOIUrl":null,"url":null,"abstract":"<div><div>In order to safely and efficiently operate pressurized water reactors, it is essential to monitor neutron flux and power distributions throughout the operation cycle. Most of currently operated reactors have in-core instrumentation systems capable of taking assembly-wise axially integrated flux measurements. However, commercial reactors typically possess few fuel assemblies that contain guide tubes for in-core instrumentation and it is necessary to estimate power values at the remaining fuel assemblies. This work employs gaussian process regression, a non-parametric supervised learning method, to predict the power distribution over the entire core using only measured data. The OpenMC Monte Carlo code was employed to emulate detector signals from instrumented assemblies as well as to produce reference values at non-instrumented assemblies against which the regression method was validated. The mean and maximum relative discrepancies were below 0.8% and 2.5%, respectively, in a scenario with full detector availability. Considering the failure of a single detector, the maximum relative discrepancy did not exceed 5.3%, showing the feasibility of the model as an operation monitoring system capable of real-time reconstruction of the core power distribution.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"223 ","pages":"Article 111581"},"PeriodicalIF":2.3000,"publicationDate":"2025-06-06","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":"{\"title\":\"Power distribution reconstruction from in-core detector measurements using gaussian process regression\",\"authors\":\"Artur Souza e Silva, Alessandro da Cruz Gonçalves, Willian Vieira de Abreu, Adilson Costa da Silva, Aquilino Senra Martinez\",\"doi\":\"10.1016/j.anucene.2025.111581\",\"DOIUrl\":null,\"url\":null,\"abstract\":\"<div><div>In order to safely and efficiently operate pressurized water reactors, it is essential to monitor neutron flux and power distributions throughout the operation cycle. Most of currently operated reactors have in-core instrumentation systems capable of taking assembly-wise axially integrated flux measurements. However, commercial reactors typically possess few fuel assemblies that contain guide tubes for in-core instrumentation and it is necessary to estimate power values at the remaining fuel assemblies. This work employs gaussian process regression, a non-parametric supervised learning method, to predict the power distribution over the entire core using only measured data. The OpenMC Monte Carlo code was employed to emulate detector signals from instrumented assemblies as well as to produce reference values at non-instrumented assemblies against which the regression method was validated. The mean and maximum relative discrepancies were below 0.8% and 2.5%, respectively, in a scenario with full detector availability. Considering the failure of a single detector, the maximum relative discrepancy did not exceed 5.3%, showing the feasibility of the model as an operation monitoring system capable of real-time reconstruction of the core power distribution.</div></div>\",\"PeriodicalId\":8006,\"journal\":{\"name\":\"Annals of Nuclear Energy\",\"volume\":\"223 \",\"pages\":\"Article 111581\"},\"PeriodicalIF\":2.3000,\"publicationDate\":\"2025-06-06\",\"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/S0306454925003986\",\"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/S0306454925003986","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}
Power distribution reconstruction from in-core detector measurements using gaussian process regression
In order to safely and efficiently operate pressurized water reactors, it is essential to monitor neutron flux and power distributions throughout the operation cycle. Most of currently operated reactors have in-core instrumentation systems capable of taking assembly-wise axially integrated flux measurements. However, commercial reactors typically possess few fuel assemblies that contain guide tubes for in-core instrumentation and it is necessary to estimate power values at the remaining fuel assemblies. This work employs gaussian process regression, a non-parametric supervised learning method, to predict the power distribution over the entire core using only measured data. The OpenMC Monte Carlo code was employed to emulate detector signals from instrumented assemblies as well as to produce reference values at non-instrumented assemblies against which the regression method was validated. The mean and maximum relative discrepancies were below 0.8% and 2.5%, respectively, in a scenario with full detector availability. Considering the failure of a single detector, the maximum relative discrepancy did not exceed 5.3%, showing the feasibility of the model as an operation monitoring system capable of real-time reconstruction of the core power distribution.
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.