Guangdong Liu, He Zhu, Zhui Zhang, G. Zhang, Guitao Cao, Lin Tan, J. Qi
{"title":"Research on Fatigue Analysis Method of Nuclear Equipment Under Ocean Conditions","authors":"Guangdong Liu, He Zhu, Zhui Zhang, G. Zhang, Guitao Cao, Lin Tan, J. Qi","doi":"10.1115/icone29-92711","DOIUrl":null,"url":null,"abstract":"\n Under the conditions of the marine environment (wind, wave, current), the floating platform on the ocean undergoes heeling, trimming, rolling, pitching, swaying, surging, heaving movements. The floating reactor on the floating platform within the design life, in addition to withstand the low-frequency fatigue caused by primary loop temperature and pressure, it also has to withstand the inertial force generated by the sway of the wave for the service period. The inertial force generated by the wave is a constantly changing dynamic load. Alternating stresses inside of the structure may cause fatigue damage to the structure. In order to estimate the fatigue life of floating reactor equipment under various ocean conditions, a finite element analysis model of equipment was established to carry out research for fatigue analysis methods under sway loads, meanwhile the operating temperature and pressure loads were considered. The probability of sway at each angle obeys the Rayleigh distribution, through the analysis of the status for the platform, it can estimate the number of swings at each angle. Based on Miner linear cumulative damage theory, the cumulative fatigue usage factors meet the requirements of the ASME BPVC III NB-3220 code. This analysis method provides a reference for the fatigue analysis of the floating reactor nuclear equipment.","PeriodicalId":317622,"journal":{"name":"Volume 10: Advanced Methods of Manufacturing for Nuclear Reactors and Components","volume":"2014 1","pages":"0"},"PeriodicalIF":0.0000,"publicationDate":"2022-08-08","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":null,"platform":"Semanticscholar","paperid":null,"PeriodicalName":"Volume 10: Advanced Methods of Manufacturing for Nuclear Reactors and Components","FirstCategoryId":"1085","ListUrlMain":"https://doi.org/10.1115/icone29-92711","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
Under the conditions of the marine environment (wind, wave, current), the floating platform on the ocean undergoes heeling, trimming, rolling, pitching, swaying, surging, heaving movements. The floating reactor on the floating platform within the design life, in addition to withstand the low-frequency fatigue caused by primary loop temperature and pressure, it also has to withstand the inertial force generated by the sway of the wave for the service period. The inertial force generated by the wave is a constantly changing dynamic load. Alternating stresses inside of the structure may cause fatigue damage to the structure. In order to estimate the fatigue life of floating reactor equipment under various ocean conditions, a finite element analysis model of equipment was established to carry out research for fatigue analysis methods under sway loads, meanwhile the operating temperature and pressure loads were considered. The probability of sway at each angle obeys the Rayleigh distribution, through the analysis of the status for the platform, it can estimate the number of swings at each angle. Based on Miner linear cumulative damage theory, the cumulative fatigue usage factors meet the requirements of the ASME BPVC III NB-3220 code. This analysis method provides a reference for the fatigue analysis of the floating reactor nuclear equipment.
在海洋环境(风、浪、流)的作用下,海洋上的浮动平台会发生倾侧、横倾、翻滚、俯仰、摇摆、涌动、起伏等运动。在设计使用寿命内的浮动平台上的浮动堆,除了要承受一次回路温度和压力引起的低频疲劳外,还要承受服役期内波浪摆动产生的惯性力。波浪所产生的惯性力是一个不断变化的动载荷。结构内部的交变应力会引起结构的疲劳损伤。为了估算各种海洋工况下浮动堆设备的疲劳寿命,建立了浮动堆设备有限元分析模型,在考虑工作温度和压力载荷的情况下,对摆动载荷下的疲劳分析方法进行了研究。各角度的摆动概率服从瑞利分布,通过对平台状态的分析,可以估计出各角度的摆动次数。基于Miner线性累积损伤理论,累积疲劳使用系数满足ASME BPVC III NB-3220规范的要求。该分析方法可为浮式反应堆核设备的疲劳分析提供参考。