Long Cai , Zhe Jiao , Dongbo Qi , Xuezhi Ding , Yuan Xu , Yun Long
{"title":"轴封式反应堆冷却剂泵叶轮及轴系可靠性分析","authors":"Long Cai , Zhe Jiao , Dongbo Qi , Xuezhi Ding , Yuan Xu , Yun Long","doi":"10.1016/j.anucene.2025.111884","DOIUrl":null,"url":null,"abstract":"<div><div>This study addresses the reliability issues of the axial seal main pump (RCP) impeller and shaft system under high-temperature and high-pressure water conditions. It employs fluid–structure interaction (FSI) theory and modal analysis to conduct a systematic study of dynamic characteristics and fatigue life. Using FSI simulation model, this study compares the natural frequency variations under dry and wet modal conditions to reveal the influence of added water mass on structural dynamics. Transient dynamic stress calculations are completed on the ANSYS Workbench platform. The fatigue life of the impeller is predicted using Miner’s linear cumulative damage theory and nCode DesignLife software. The results indicate that most regions of the impeller have a lifespan exceeding 7.223 × 10<sup>10</sup> cycles (approximately 92.5 years). Localized fatigue risks are identified only at the blade roots. Campbell diagram analysis shows that the rated speed of the nuclear main pump avoids the main resonant critical speeds, but attention should be paid to the influence of low-frequency excitation on stability. The findings of this study provide a theoretical basis for the structural optimization and reliability enhancement of nuclear main pumps.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"226 ","pages":"Article 111884"},"PeriodicalIF":2.3000,"publicationDate":"2025-09-18","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":"{\"title\":\"Reliability analysis of impeller and shaft system in shaft-sealed reactor coolant pump\",\"authors\":\"Long Cai , Zhe Jiao , Dongbo Qi , Xuezhi Ding , Yuan Xu , Yun Long\",\"doi\":\"10.1016/j.anucene.2025.111884\",\"DOIUrl\":null,\"url\":null,\"abstract\":\"<div><div>This study addresses the reliability issues of the axial seal main pump (RCP) impeller and shaft system under high-temperature and high-pressure water conditions. It employs fluid–structure interaction (FSI) theory and modal analysis to conduct a systematic study of dynamic characteristics and fatigue life. Using FSI simulation model, this study compares the natural frequency variations under dry and wet modal conditions to reveal the influence of added water mass on structural dynamics. Transient dynamic stress calculations are completed on the ANSYS Workbench platform. The fatigue life of the impeller is predicted using Miner’s linear cumulative damage theory and nCode DesignLife software. The results indicate that most regions of the impeller have a lifespan exceeding 7.223 × 10<sup>10</sup> cycles (approximately 92.5 years). Localized fatigue risks are identified only at the blade roots. Campbell diagram analysis shows that the rated speed of the nuclear main pump avoids the main resonant critical speeds, but attention should be paid to the influence of low-frequency excitation on stability. The findings of this study provide a theoretical basis for the structural optimization and reliability enhancement of nuclear main pumps.</div></div>\",\"PeriodicalId\":8006,\"journal\":{\"name\":\"Annals of Nuclear Energy\",\"volume\":\"226 \",\"pages\":\"Article 111884\"},\"PeriodicalIF\":2.3000,\"publicationDate\":\"2025-09-18\",\"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/S0306454925007017\",\"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}","platform":"Semanticscholar","paperid":null,"PeriodicalName":"Annals of Nuclear Energy","FirstCategoryId":"5","ListUrlMain":"https://www.sciencedirect.com/science/article/pii/S0306454925007017","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}
Reliability analysis of impeller and shaft system in shaft-sealed reactor coolant pump
This study addresses the reliability issues of the axial seal main pump (RCP) impeller and shaft system under high-temperature and high-pressure water conditions. It employs fluid–structure interaction (FSI) theory and modal analysis to conduct a systematic study of dynamic characteristics and fatigue life. Using FSI simulation model, this study compares the natural frequency variations under dry and wet modal conditions to reveal the influence of added water mass on structural dynamics. Transient dynamic stress calculations are completed on the ANSYS Workbench platform. The fatigue life of the impeller is predicted using Miner’s linear cumulative damage theory and nCode DesignLife software. The results indicate that most regions of the impeller have a lifespan exceeding 7.223 × 1010 cycles (approximately 92.5 years). Localized fatigue risks are identified only at the blade roots. Campbell diagram analysis shows that the rated speed of the nuclear main pump avoids the main resonant critical speeds, but attention should be paid to the influence of low-frequency excitation on stability. The findings of this study provide a theoretical basis for the structural optimization and reliability enhancement of nuclear main pumps.
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.