Multiphysics Computational Modeling of Nuclear Reactors Small Size Through the Coupling of Serpent Codes and Fluent

Erik Lago, Dany Sanchez Dominguez, L. Mazaira
{"title":"Multiphysics Computational Modeling of Nuclear Reactors Small Size Through the Coupling of Serpent Codes and Fluent","authors":"Erik Lago, Dany Sanchez Dominguez, L. Mazaira","doi":"10.15392/2319-0612.2024.2425","DOIUrl":null,"url":null,"abstract":"The study of nuclear energy using computational codes has been widely explored by nuclear engineering researchers through various calculations over the years, with emphasis on neutron and thermo-hydraulic calculations. The need for designing a reactor model that would produce energy at a lower cost per MWh highlighted the importance of Small Modular Reactor (SMR) reactors. Development: The present work aims to carry out a study related to the coupling of two computational codes, SERPENT and ANSYS FLUENT, using an SMR PWR reactor model (Pressurized Water Reactor) from the company B&W Generation, called mPower. Methods: The geometry of a pin of the mPower reactor was modeled and neutronics analyses of the model were performed using SERPENT code, while thermo-hydraulic analysis was simulated using FLUENT code. A coupling algorithm between these two simulation tools was built to automate the process of obtaining operational conditions for the effective operation of the reactor. Results: This work enabled the development of a tool that performs the multiphysics coupling between neutronic and thermos-hydraulic phenomena on mPower fuel pin. Conclusion: Multiphysics simulation, which considers the interaction between neutronic and thermal dynamics, provides an enhanced understanding of reactor operation. In this simulation, the power distribution generated by the neutronic code is used as input for the thermo-hydraulic code. Conversely, the temperature distribution obtained from the thermo-hydraulic simulation is fed back into a subsequent iteration of the neutronic analysis, thus achieving a coupling between these phenomena.  To obtain accurate estimates for the power and temperature distributions, an automated process based on Python programming was implemented.","PeriodicalId":9203,"journal":{"name":"Brazilian Journal of Radiation Sciences","volume":null,"pages":null},"PeriodicalIF":0.0000,"publicationDate":"2024-07-05","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":null,"platform":"Semanticscholar","paperid":null,"PeriodicalName":"Brazilian Journal of Radiation Sciences","FirstCategoryId":"1085","ListUrlMain":"https://doi.org/10.15392/2319-0612.2024.2425","RegionNum":0,"RegionCategory":null,"ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"","JCRName":"","Score":null,"Total":0}
引用次数: 0

Abstract

The study of nuclear energy using computational codes has been widely explored by nuclear engineering researchers through various calculations over the years, with emphasis on neutron and thermo-hydraulic calculations. The need for designing a reactor model that would produce energy at a lower cost per MWh highlighted the importance of Small Modular Reactor (SMR) reactors. Development: The present work aims to carry out a study related to the coupling of two computational codes, SERPENT and ANSYS FLUENT, using an SMR PWR reactor model (Pressurized Water Reactor) from the company B&W Generation, called mPower. Methods: The geometry of a pin of the mPower reactor was modeled and neutronics analyses of the model were performed using SERPENT code, while thermo-hydraulic analysis was simulated using FLUENT code. A coupling algorithm between these two simulation tools was built to automate the process of obtaining operational conditions for the effective operation of the reactor. Results: This work enabled the development of a tool that performs the multiphysics coupling between neutronic and thermos-hydraulic phenomena on mPower fuel pin. Conclusion: Multiphysics simulation, which considers the interaction between neutronic and thermal dynamics, provides an enhanced understanding of reactor operation. In this simulation, the power distribution generated by the neutronic code is used as input for the thermo-hydraulic code. Conversely, the temperature distribution obtained from the thermo-hydraulic simulation is fed back into a subsequent iteration of the neutronic analysis, thus achieving a coupling between these phenomena.  To obtain accurate estimates for the power and temperature distributions, an automated process based on Python programming was implemented.
通过 Serpent 代码和 Fluent 耦合进行小型核反应堆多物理场计算建模
多年来,核工程研究人员通过各种计算广泛探索了利用计算代码研究核能的方法,重点是中子和热液计算。设计一种能以较低的每兆瓦时成本生产能源的反应堆模型的需求,凸显了小型模块化反应堆(SMR)的重要性。开发:目前的工作旨在利用 B&W Generation 公司名为 mPower 的 SMR PWR 反应堆模型(压水反应堆),对 SERPENT 和 ANSYS FLUENT 这两种计算代码的耦合进行研究。方法对 mPower 反应堆的一个销钉的几何形状进行建模,并使用 SERPENT 代码对模型进行中子学分析,同时使用 FLUENT 代码模拟热液分析。建立了这两种模拟工具之间的耦合算法,以自动获取反应堆有效运行的操作条件。结果:这项工作开发了一种工具,可对 mPower 燃料销进行中子现象和热液现象的多物理场耦合。结论多物理场模拟考虑了中子动力学和热动力学之间的相互作用,有助于加深对反应堆运行的理解。在该模拟中,中子代码生成的功率分布被用作热液代码的输入。反之,从热-水力模拟中获得的温度分布会反馈到中子分析的后续迭代中,从而实现这些现象之间的耦合。 为了获得功率和温度分布的精确估算值,采用了基于 Python 编程的自动化流程。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
求助全文
约1分钟内获得全文 求助全文
来源期刊
自引率
0.00%
发文量
0
×
引用
GB/T 7714-2015
复制
MLA
复制
APA
复制
导出至
BibTeX EndNote RefMan NoteFirst NoteExpress
×
提示
您的信息不完整,为了账户安全,请先补充。
现在去补充
×
提示
您因"违规操作"
具体请查看互助需知
我知道了
×
提示
确定
请完成安全验证×
copy
已复制链接
快去分享给好友吧!
我知道了
右上角分享
点击右上角分享
0
联系我们:info@booksci.cn Book学术提供免费学术资源搜索服务,方便国内外学者检索中英文文献。致力于提供最便捷和优质的服务体验。 Copyright © 2023 布克学术 All rights reserved.
京ICP备2023020795号-1
ghs 京公网安备 11010802042870号
Book学术文献互助
Book学术文献互助群
群 号:481959085
Book学术官方微信