M.A. Uvakin, A.L. Nikolaev, M.V. Antipov, I.V. Makhin
{"title":"Artificial intelligence methods application for reactor dynamics predicting in the tasks of maneuverable modes safety assessment","authors":"M.A. Uvakin, A.L. Nikolaev, M.V. Antipov, I.V. Makhin","doi":"10.1016/j.anucene.2025.111248","DOIUrl":null,"url":null,"abstract":"<div><div>The work aimed to the development of a methodology for calculating safety assessment of VVER reactor plants in maneuvering modes. This methodology was developed at OKB “GIDROPRESS” to solve the problem of conducting safety analyzes of high-power VVER reactor plants in a flexible operation mode. Performing such work directly requires significant computing resources and multi-parameter expert assessments. Therefore, the main direction of development was the use of a numerical method using neural network models. In particular, the possibility of efficiency increasing of calculations show in terms of choosing the moment in time when the occurrence of the initial event leads to the most conservative results.</div><div>In this work, we study the possibilities of further development of the method by constructing neural networks with deep learning aimed at predicting the development of non-stationary processes, taking into account a large number and complex relationships of available parameters. The capabilities of convolution and recursive architectures for constructing neural networks analyzed to estimate the reactor plant dynamics, taking into account maneuvering after an accident occurs. The analysis examines the interpretability of the results in terms of accounting for xenon transients, water exchange operations, and control movement. For software implementation of the method, the VELETMA/GP program is used.</div><div>Based on the results of the work, conclusions drawn about the practical significance of the methods used for solving the tasks set for the calculation substantiation of designs of reactor plants with VVER in maneuvering modes. The work uses both the experience of computational justification and the results of validating full-scale tests of maneuvering modes on modern high-power VVER reactors.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"215 ","pages":"Article 111248"},"PeriodicalIF":1.9000,"publicationDate":"2025-02-08","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/S0306454925000659","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 work aimed to the development of a methodology for calculating safety assessment of VVER reactor plants in maneuvering modes. This methodology was developed at OKB “GIDROPRESS” to solve the problem of conducting safety analyzes of high-power VVER reactor plants in a flexible operation mode. Performing such work directly requires significant computing resources and multi-parameter expert assessments. Therefore, the main direction of development was the use of a numerical method using neural network models. In particular, the possibility of efficiency increasing of calculations show in terms of choosing the moment in time when the occurrence of the initial event leads to the most conservative results.
In this work, we study the possibilities of further development of the method by constructing neural networks with deep learning aimed at predicting the development of non-stationary processes, taking into account a large number and complex relationships of available parameters. The capabilities of convolution and recursive architectures for constructing neural networks analyzed to estimate the reactor plant dynamics, taking into account maneuvering after an accident occurs. The analysis examines the interpretability of the results in terms of accounting for xenon transients, water exchange operations, and control movement. For software implementation of the method, the VELETMA/GP program is used.
Based on the results of the work, conclusions drawn about the practical significance of the methods used for solving the tasks set for the calculation substantiation of designs of reactor plants with VVER in maneuvering modes. The work uses both the experience of computational justification and the results of validating full-scale tests of maneuvering modes on modern high-power VVER reactors.
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.