{"title":"Prediction of core unmeasurable parameters during loss of coolant accident using deep neural network method","authors":"Milad Moradi, Mohsen Ghafari","doi":"10.1016/j.pnucene.2025.105760","DOIUrl":null,"url":null,"abstract":"<div><div>The parameters within the reactor core would be categorized into two different groups of measurable and unmeasurable parameters. The determination of unmeasurable parameters, such as void fraction and critical heat flux, plays a significant and fundamental role in predicting the occurrence of accidents and emergency situations within the reactor. The utilization of deep neural networks represents one of the methods for accurate and reliable estimation of these parameters. Such estimations facilitate the implementation of necessary measures to prevent accidents or mitigate their consequences. In this study, three deep neural network models namely LSTM, TFT, and NBEATS are employed for void fraction prediction within the reactor core after Loss of Coolant Accident (LOCA). The neural network training will be performed without covariates, using past covariates and using future covariates. The results reveal that the TFT neural network, trained with future covariates (e.g. pressure, temperature, water velocity and steam velocity) yields the lowest error.</div></div>","PeriodicalId":20617,"journal":{"name":"Progress in Nuclear Energy","volume":"185 ","pages":""},"PeriodicalIF":3.3000,"publicationDate":"2025-04-05","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":null,"platform":"Semanticscholar","paperid":null,"PeriodicalName":"Progress in Nuclear Energy","FirstCategoryId":"5","ListUrlMain":"https://www.sciencedirect.com/science/article/pii/S0149197025001581","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 parameters within the reactor core would be categorized into two different groups of measurable and unmeasurable parameters. The determination of unmeasurable parameters, such as void fraction and critical heat flux, plays a significant and fundamental role in predicting the occurrence of accidents and emergency situations within the reactor. The utilization of deep neural networks represents one of the methods for accurate and reliable estimation of these parameters. Such estimations facilitate the implementation of necessary measures to prevent accidents or mitigate their consequences. In this study, three deep neural network models namely LSTM, TFT, and NBEATS are employed for void fraction prediction within the reactor core after Loss of Coolant Accident (LOCA). The neural network training will be performed without covariates, using past covariates and using future covariates. The results reveal that the TFT neural network, trained with future covariates (e.g. pressure, temperature, water velocity and steam velocity) yields the lowest error.
期刊介绍:
Progress in Nuclear Energy is an international review journal covering all aspects of nuclear science and engineering. In keeping with the maturity of nuclear power, articles on safety, siting and environmental problems are encouraged, as are those associated with economics and fuel management. However, basic physics and engineering will remain an important aspect of the editorial policy. Articles published are either of a review nature or present new material in more depth. They are aimed at researchers and technically-oriented managers working in the nuclear energy field.
Please note the following:
1) PNE seeks high quality research papers which are medium to long in length. Short research papers should be submitted to the journal Annals in Nuclear Energy.
2) PNE reserves the right to reject papers which are based solely on routine application of computer codes used to produce reactor designs or explain existing reactor phenomena. Such papers, although worthy, are best left as laboratory reports whereas Progress in Nuclear Energy seeks papers of originality, which are archival in nature, in the fields of mathematical and experimental nuclear technology, including fission, fusion (blanket physics, radiation damage), safety, materials aspects, economics, etc.
3) Review papers, which may occasionally be invited, are particularly sought by the journal in these fields.