New insight into fatigue life of modified 9Cr-1Mo steel in liquid lead–bismuth environment and life prediction considering environmental factors

IF 1.9 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Nuclear Engineering and Design Pub Date : 2024-10-30 DOI:10.1016/j.nucengdes.2024.113648

Shouwen Shi , Wei Huang , Gaoyuan Xie , Weibin Li , Longyi Yang , Qiang Lin , Gang Chen , Xu Chen

{"title":"New insight into fatigue life of modified 9Cr-1Mo steel in liquid lead–bismuth environment and life prediction considering environmental factors","authors":"Shouwen Shi , Wei Huang , Gaoyuan Xie , Weibin Li , Longyi Yang , Qiang Lin , Gang Chen , Xu Chen","doi":"10.1016/j.nucengdes.2024.113648","DOIUrl":null,"url":null,"abstract":"<div><div>The fatigue life of modified 9Cr-1Mo steel in liquid lead bismuth eutectic (LBE) at different strain amplitudes, temperatures and oxygen concentrations are analyzed. A liquid metal embrittlement (LME) factor of plastic strain is proposed to account for the reduced fatigue life induced by LME effect, which is also found to correlate well with tensile elongation in LBE. In low oxygen content LBE, the LME effect is influenced by temperature instead of plastic strain amplitude. While in high oxygen content LBE, the plastic LME factor is found to decrease exponentially with increasing plastic strain amplitude. Based on these findings, a fatigue life prediction model is proposed taking into account of different environmental influencing factors. In total, 86 data points are used with 70 % data points for independent validation only. Regardless of the discrepancy in fatigue life from different sources, good prediction results are still achieved with 98 % data points fall within ± 3 error band and 75 % data points fall within ± 2 error band.</div></div>","PeriodicalId":19170,"journal":{"name":"Nuclear Engineering and Design","volume":"429 ","pages":"Article 113648"},"PeriodicalIF":1.9000,"publicationDate":"2024-10-30","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":null,"platform":"Semanticscholar","paperid":null,"PeriodicalName":"Nuclear Engineering and Design","FirstCategoryId":"5","ListUrlMain":"https://www.sciencedirect.com/science/article/pii/S0029549324007489","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}

引用次数: 0

Abstract

The fatigue life of modified 9Cr-1Mo steel in liquid lead bismuth eutectic (LBE) at different strain amplitudes, temperatures and oxygen concentrations are analyzed. A liquid metal embrittlement (LME) factor of plastic strain is proposed to account for the reduced fatigue life induced by LME effect, which is also found to correlate well with tensile elongation in LBE. In low oxygen content LBE, the LME effect is influenced by temperature instead of plastic strain amplitude. While in high oxygen content LBE, the plastic LME factor is found to decrease exponentially with increasing plastic strain amplitude. Based on these findings, a fatigue life prediction model is proposed taking into account of different environmental influencing factors. In total, 86 data points are used with 70 % data points for independent validation only. Regardless of the discrepancy in fatigue life from different sources, good prediction results are still achieved with 98 % data points fall within ± 3 error band and 75 % data points fall within ± 2 error band.

查看原文本刊更多论文

对液态铅铋环境中改性 9Cr-1Mo 钢疲劳寿命的新认识以及考虑环境因素的寿命预测

分析了液态铅铋共晶（LBE）中改性 9Cr-1Mo 钢在不同应变振幅、温度和氧浓度下的疲劳寿命。提出了塑性应变的液态金属脆化（LME）因子，以解释 LME 效应引起的疲劳寿命降低，该因子还与 LBE 中的拉伸延伸率密切相关。在低氧含量的鳞片状结晶器中，LME效应受温度而不是塑性应变振幅的影响。而在高含氧量的鳞片板材中，塑性 LME 因子会随着塑性应变振幅的增大而呈指数下降。基于这些发现，我们提出了一个考虑到不同环境影响因素的疲劳寿命预测模型。总共使用了 86 个数据点，其中 70% 的数据点仅用于独立验证。尽管不同来源的疲劳寿命存在差异，但仍取得了良好的预测结果，98% 的数据点在±3 的误差范围内，75% 的数据点在±2 的误差范围内。

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

Nuclear Engineering and Design 工程技术-核科学技术

CiteScore

3.40

自引率

11.80%

发文量

377

审稿时长

5 months

期刊介绍： Nuclear Engineering and Design covers the wide range of disciplines involved in the engineering, design, safety and construction of nuclear fission reactors. The Editors welcome papers both on applied and innovative aspects and developments in nuclear science and technology. Fundamentals of Reactor Design include: • Thermal-Hydraulics and Core Physics • Safety Analysis, Risk Assessment (PSA) • Structural and Mechanical Engineering • Materials Science • Fuel Behavior and Design • Structural Plant Design • Engineering of Reactor Components • Experiments Aspects beyond fundamentals of Reactor Design covered: • Accident Mitigation Measures • Reactor Control Systems • Licensing Issues • Safeguard Engineering • Economy of Plants • Reprocessing / Waste Disposal • Applications of Nuclear Energy • Maintenance • Decommissioning Papers on new reactor ideas and developments (Generation IV reactors) such as inherently safe modular HTRs, High Performance LWRs/HWRs and LMFBs/GFR will be considered; Actinide Burners, Accelerator Driven Systems, Energy Amplifiers and other special designs of power and research reactors and their applications are also encouraged.