首页> 外文期刊>International Journal of Fatigue >Thermomechanical and isothermal fatigue behavior of 347 and 316L austenitic stainless tube and pipe steels
【24h】

Thermomechanical and isothermal fatigue behavior of 347 and 316L austenitic stainless tube and pipe steels

机译:347和316L奥氏体不锈钢管和钢管的热机械和等温疲劳行为

获取原文
获取原文并翻译 | 示例
       

摘要

Many components of nuclear power plant piping systems are made of austenitic stainless steels. These structures undergo degradation by thermomechanical loading caused by thermal transients and stratifi-cations. In scientific literature, most of the studies deal with this problem under isothermal fatigue con-ditions, which is different from the typical service conditions. In addition, less attention has been paid to thermo-mechanical fatigue (TMF). This work aims to understand and compare the cyclic deformation behavior during TMF and isothermal fatigue (IF) testing in air for two of the most commonly used grades of austenitic stainless tube and pipe (TP) steel, the non-stabilized TP 316L and the niobium-stabilized TP 347, under light water reactor relevant temperature conditions. Three types of tests, i.e. in-phase, out-of-phase TMF in the 100-340 °C temperature range, and IF tests at the maximum temperature T_(max) of TMF were performed. All the tests were carried out under total strain control, for two different mechan-ical strain amplitudes (Δε_(mech)/2 = 0.3% and 0.5%). Results revealed that irrespective of the tested strain amplitude and material, in-phase TMF showed a higher lifetime over out-of-phase TMF and IF at T_(max). A crossover in fatigue lifetime was observed in TP 316L between out-of-phase TMF and IF test at T_(max) with decreasing strain amplitude. In TP 347, out-of-phase TMF and IF test at T_(max) showed similar fatigue life-times for both strain amplitudes. Finally, three lifetime prediction models were selected and compared to evaluate the possibility of estimating TMF lifetime by using IF data. Satisfactory predictions were obtained from all the prediction approaches. © 2010 Elsevier Ltd. All rights reserved.
机译:核电站管道系统的许多组件均由奥氏体不锈钢制成。这些结构由于热瞬变和分层引起的热机械载荷而退化。在科学文献中,大多数研究都是在等温疲劳条件下处理此问题的,这与典型的使用条件不同。此外,对热机械疲劳(TMF)的关注较少。这项工作旨在了解和比较空气中TMF和等温疲劳(IF)测试中两种最常用的奥氏体不锈钢管(TP)钢,非稳定TP 316L和铌的循环变形行为-在轻水反应堆相关温度条件下稳定的TP 347。进行了三种类型的测试,即100-340°C温度范围内的同相,异相TMF,以及在TMF的最高温度T_(max)下进行IF测试。所有测试均在总应变控制下针对两个不同的机械应变幅度(Δε_(mech)/ 2 = 0.3%和0.5%)进行。结果表明,与测试的应变幅度和材料无关,在T_(max)时,同相TMF的寿命高于异相TMF和IF。在TP_316L中,在T_(max)下,随着应变幅度的减小,疲劳寿命的过渡发生在异相TMF和IF测试之间。在TP 347中,在T_(max)处进行的异相TMF和IF测试表明,两种应变幅度的疲劳寿命相似。最后,选择了三个寿命预测模型并进行了比较,以评估使用IF数据估算TMF寿命的可能性。从所有预测方法中获得了令人满意的预测。 ©2010 ElsevierLtd。保留所有权利。

著录项

相似文献

  • 外文文献
  • 中文文献
  • 专利
获取原文

客服邮箱:kefu@zhangqiaokeyan.com

京公网安备:11010802029741号 ICP备案号:京ICP备15016152号-6 六维联合信息科技 (北京) 有限公司©版权所有
  • 客服微信

  • 服务号