A Step Towards Rules to Identify Bounding Conditions in Terms of Fatigue Damage for NPP Operational Transients

Feng Lv, Zhengyu Zhou, Zhilin Chen, Han Liu, Zihao Zheng
{"title":"A Step Towards Rules to Identify Bounding Conditions in Terms of Fatigue Damage for NPP Operational Transients","authors":"Feng Lv, Zhengyu Zhou, Zhilin Chen, Han Liu, Zihao Zheng","doi":"10.1115/icone29-94327","DOIUrl":null,"url":null,"abstract":"\n Mechanical components of nuclear power plant are subject to variations in temperature and pressure, which cause stress and ultimately induce fatigue damage. Usually, these variations, called operational transients, are well identified through the use of sensors and can be easily classified into design transients and associated to different reactor states and functional situations. However, a number of operational transients cannot be covered by the corresponding design transients due to temperature or pressure parameters exceeding the defined surveillance thresholds. In that case, an alternative is to find a more severe design transient to cover the operational transient, and then justify the existing design fatigue analysis remain valid. This process is today not existent in design standards and partially mentioned in standards such as RSE-M, yet it is critical for the safe operation of plants especially in the domain of Long Term Operation (LTO). In this paper, a set of mechanical criteria is developed to compare the severity between transients, which include four aspects: maximum stress state, minimum stress state, alternating stress intensity and fatigue damage. A three-dimensional rain flow method is used to identify extreme stress state and to detect multiaxial stress peak and valley. As an example, a typical nozzle is assumed to endure a non-classified operational transient. The envelope analysis for this transient classification is demonstrated and a design transient is selected to cover the operational transient. The numerical simulation results show that if a design transient and an operational transient satisfy the mechanical criteria strictly, then the operational transient can be bounded by the design transient. The proposed mechanical criteria are consistent with the requirements of the RCCM and RSE-M codes in term of preventing fatigue damage.","PeriodicalId":220265,"journal":{"name":"Volume 6: Nuclear Codes, Standards, Licensing, and Regulatory Issues","volume":"110 2 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 6: Nuclear Codes, Standards, Licensing, and Regulatory Issues","FirstCategoryId":"1085","ListUrlMain":"https://doi.org/10.1115/icone29-94327","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

Mechanical components of nuclear power plant are subject to variations in temperature and pressure, which cause stress and ultimately induce fatigue damage. Usually, these variations, called operational transients, are well identified through the use of sensors and can be easily classified into design transients and associated to different reactor states and functional situations. However, a number of operational transients cannot be covered by the corresponding design transients due to temperature or pressure parameters exceeding the defined surveillance thresholds. In that case, an alternative is to find a more severe design transient to cover the operational transient, and then justify the existing design fatigue analysis remain valid. This process is today not existent in design standards and partially mentioned in standards such as RSE-M, yet it is critical for the safe operation of plants especially in the domain of Long Term Operation (LTO). In this paper, a set of mechanical criteria is developed to compare the severity between transients, which include four aspects: maximum stress state, minimum stress state, alternating stress intensity and fatigue damage. A three-dimensional rain flow method is used to identify extreme stress state and to detect multiaxial stress peak and valley. As an example, a typical nozzle is assumed to endure a non-classified operational transient. The envelope analysis for this transient classification is demonstrated and a design transient is selected to cover the operational transient. The numerical simulation results show that if a design transient and an operational transient satisfy the mechanical criteria strictly, then the operational transient can be bounded by the design transient. The proposed mechanical criteria are consistent with the requirements of the RCCM and RSE-M codes in term of preventing fatigue damage.
核电厂运行瞬态疲劳损伤边界条件确定规则的一步
核电站的机械部件受到温度和压力变化的影响,这些变化会产生应力,最终导致疲劳损伤。通常,这些变化被称为运行瞬态,通过使用传感器可以很好地识别,并且可以很容易地分类为设计瞬态,并与不同的反应堆状态和功能情况相关联。然而,由于温度或压力参数超过定义的监视阈值,一些操作瞬态不能被相应的设计瞬态覆盖。在这种情况下,另一种选择是找到一个更严重的设计瞬态来覆盖操作瞬态,然后证明现有的设计疲劳分析仍然有效。这一过程目前在设计标准中不存在,在RSE-M等标准中也有部分提及,但它对工厂的安全运行至关重要,特别是在长期运行(LTO)领域。本文从最大应力状态、最小应力状态、交变应力强度和疲劳损伤四个方面,建立了一套比较瞬变强度的力学准则。采用三维雨流法识别极端应力状态,检测多轴应力峰谷。作为一个例子,假设一个典型的喷嘴承受了一个非分类的工作瞬变。演示了这种暂态分类的包络分析,并选择了一种设计暂态来覆盖运行暂态。数值模拟结果表明,如果设计暂态和运行暂态都严格满足力学准则,则运行暂态可以以设计暂态为界。提出的力学准则在防止疲劳损伤方面符合RCCM和RSE-M规范的要求。
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:604180095
Book学术官方微信