{"title":"NHR200-II燃料棒在湍流轴流中的模态特性分析","authors":"Musen Lin, Dingqu Wang, Junzheng Zheng, Yueyuan Jiang","doi":"10.1016/j.anucene.2024.111164","DOIUrl":null,"url":null,"abstract":"<div><div>The dynamics of vibrating fuel rods under axial fluid flows in a 200 MW nuclear heating reactor (NHR200-II) was analyzed through Fluid-Structure Interaction (FSI) simulations. Various inflow velocities and turbulence inlet conditions were considered to assess their influence on the system’s modal properties. The turbulent fluid flow was modelled by Unsteady Reynolds-Averaged Navier–Stokes (URANS) approach, while the rod was treated as an elastic solid. Numerical simulations were conducted utilizing the two-way coupling FSI solver in the commercial code LS-DYNA. The computational results indicate that the vibrating frequency remains largely insensitive to inflow velocities ranging from 0 to 6 m/s, whereas modal damping ratio increases with higher velocities. Turbulence inlet conditions were found to have a negligible effect on rod vibrations in specified inflow velocities. Furthermore, the added mass and damping for an inflow velocity of 1.0 m/s were evaluated as a demonstration and successfully integrated into the relevant structural solver.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"213 ","pages":"Article 111164"},"PeriodicalIF":2.3000,"publicationDate":"2025-04-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":"{\"title\":\"Analysis of the modal characteristics of NHR200-II fuel rods in turbulent axial flow\",\"authors\":\"Musen Lin, Dingqu Wang, Junzheng Zheng, Yueyuan Jiang\",\"doi\":\"10.1016/j.anucene.2024.111164\",\"DOIUrl\":null,\"url\":null,\"abstract\":\"<div><div>The dynamics of vibrating fuel rods under axial fluid flows in a 200 MW nuclear heating reactor (NHR200-II) was analyzed through Fluid-Structure Interaction (FSI) simulations. Various inflow velocities and turbulence inlet conditions were considered to assess their influence on the system’s modal properties. The turbulent fluid flow was modelled by Unsteady Reynolds-Averaged Navier–Stokes (URANS) approach, while the rod was treated as an elastic solid. Numerical simulations were conducted utilizing the two-way coupling FSI solver in the commercial code LS-DYNA. The computational results indicate that the vibrating frequency remains largely insensitive to inflow velocities ranging from 0 to 6 m/s, whereas modal damping ratio increases with higher velocities. Turbulence inlet conditions were found to have a negligible effect on rod vibrations in specified inflow velocities. Furthermore, the added mass and damping for an inflow velocity of 1.0 m/s were evaluated as a demonstration and successfully integrated into the relevant structural solver.</div></div>\",\"PeriodicalId\":8006,\"journal\":{\"name\":\"Annals of Nuclear Energy\",\"volume\":\"213 \",\"pages\":\"Article 111164\"},\"PeriodicalIF\":2.3000,\"publicationDate\":\"2025-04-01\",\"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/S0306454924008272\",\"RegionNum\":3,\"RegionCategory\":\"工程技术\",\"ArticlePicture\":[],\"TitleCN\":null,\"AbstractTextCN\":null,\"PMCID\":null,\"EPubDate\":\"2024/12/26 0:00:00\",\"PubModel\":\"Epub\",\"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/S0306454924008272","RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"2024/12/26 0:00:00","PubModel":"Epub","JCR":"Q1","JCRName":"NUCLEAR SCIENCE & TECHNOLOGY","Score":null,"Total":0}
引用次数: 0
摘要
通过流固耦合(FSI)仿真,分析了200 MW核加热堆(NHR200-II)中燃料棒在轴向流体作用下的振动动力学。考虑了不同的流入速度和湍流进口条件,以评估它们对系统模态特性的影响。湍流流体流动采用非定常reynolds - average Navier-Stokes (URANS)方法,将杆视为弹性固体。利用商用代码LS-DYNA中的双向耦合FSI求解器进行了数值模拟。计算结果表明,在0 ~ 6 m/s范围内,振动频率对流入速度基本不敏感,而模态阻尼比随着流速的增加而增加。研究发现,在特定的流入速度下,湍流进口条件对抽油杆振动的影响可以忽略不计。此外,对流入速度为1.0 m/s时的附加质量和阻尼进行了评估,并成功地集成到相关的结构求解器中。
Analysis of the modal characteristics of NHR200-II fuel rods in turbulent axial flow
The dynamics of vibrating fuel rods under axial fluid flows in a 200 MW nuclear heating reactor (NHR200-II) was analyzed through Fluid-Structure Interaction (FSI) simulations. Various inflow velocities and turbulence inlet conditions were considered to assess their influence on the system’s modal properties. The turbulent fluid flow was modelled by Unsteady Reynolds-Averaged Navier–Stokes (URANS) approach, while the rod was treated as an elastic solid. Numerical simulations were conducted utilizing the two-way coupling FSI solver in the commercial code LS-DYNA. The computational results indicate that the vibrating frequency remains largely insensitive to inflow velocities ranging from 0 to 6 m/s, whereas modal damping ratio increases with higher velocities. Turbulence inlet conditions were found to have a negligible effect on rod vibrations in specified inflow velocities. Furthermore, the added mass and damping for an inflow velocity of 1.0 m/s were evaluated as a demonstration and successfully integrated into the relevant structural solver.
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.