{"title":"A rigorous method for multi-scale coupling of pebble bed and fuel pebble in high temperature gas-cooled reactor","authors":"Haojie Zhang, Ding She, Lei Shi","doi":"10.1016/j.pnucene.2025.106055","DOIUrl":null,"url":null,"abstract":"<div><div>The thermal-hydraulic design of high temperature gas-cooled reactors (HTGRs) involves a multi-scale coupling problem between the solid temperature of macroscopic pebble bed and the microscopic fuel pebble temperature. In the traditional TINTE code, the Thin Shell method is employed to address this issue, but it fails to ensure energy conservation across scales. In this paper, rigorous formulations of the temperature and heat capacity relationships between the two scales are derived from an energy conservation perspective. Based on this, an Effective Heat Capacity (EHC) method is proposed. In the EHC method, the macroscopic heat capacity is redefined to ensure consistent internal energy variations between the scales. Therefore, the EHC method can significantly reduce the number of iterations and improve the computational efficiency. Based on the DAYU3D code, some numerical tests have been conducted to demonstrate the advantages of the EHC method. The results show that the EHC approach outperforms the Thin Shell method in terms of convergence and efficiency, with a reduction in computational time of up to 35 %. This study offers a theoretical foundation for optimizing multi-scale computational methods in thermal-hydraulic analysis software for HTGRs.</div></div>","PeriodicalId":20617,"journal":{"name":"Progress in Nuclear Energy","volume":"191 ","pages":"Article 106055"},"PeriodicalIF":3.2000,"publicationDate":"2025-09-27","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/S0149197025004536","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 thermal-hydraulic design of high temperature gas-cooled reactors (HTGRs) involves a multi-scale coupling problem between the solid temperature of macroscopic pebble bed and the microscopic fuel pebble temperature. In the traditional TINTE code, the Thin Shell method is employed to address this issue, but it fails to ensure energy conservation across scales. In this paper, rigorous formulations of the temperature and heat capacity relationships between the two scales are derived from an energy conservation perspective. Based on this, an Effective Heat Capacity (EHC) method is proposed. In the EHC method, the macroscopic heat capacity is redefined to ensure consistent internal energy variations between the scales. Therefore, the EHC method can significantly reduce the number of iterations and improve the computational efficiency. Based on the DAYU3D code, some numerical tests have been conducted to demonstrate the advantages of the EHC method. The results show that the EHC approach outperforms the Thin Shell method in terms of convergence and efficiency, with a reduction in computational time of up to 35 %. This study offers a theoretical foundation for optimizing multi-scale computational methods in thermal-hydraulic analysis software for HTGRs.
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.