Investigation on the High‐Cycle Fatigue Behavior of Domestic Zr‐2.5Nb Alloy in Consideration of Notch Effects.

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Title: Investigation on the High‐Cycle Fatigue Behavior of Domestic Zr‐2.5Nb Alloy in Consideration of Notch Effects.
Authors: Ding, Wenjing1 (AUTHOR), Bao, Chen1 (AUTHOR) bchxx@163.com
Source: Fatigue & Fracture of Engineering Materials & Structures. Aug2026, Vol. 49 Issue 8, p3252-3262. 11p.
Subjects: Notch effect, High cycle fatigue, Microstructure, Fatigue life, Zirconium alloys, Nuclear reactor materials, Crack propagation
Abstract: The Zr‐2.5Nb alloy used for pressure tubes in heavy‐water reactors was utilized to investigate its high‐cycle fatigue (HCF) behavior at room temperature using both smooth and notched specimens. Based on the Theory of Critical Distance (TCD), the influence of notch geometry on fatigue behavior and life prediction was systematically examined. The fatigue failure mechanisms were further elucidated through micrographic observation. The results indicate that the main factors of fatigue life differ substantially between smooth and notched specimens, as well as crack initiation and propagation characteristics. For Zr‐2.5Nb with smaller grain sizes, typical spalling‐like stepped morphologies are observed on the fracture surface under high stress levels. Stress concentration significantly affects both the number and distribution of fatigue crack initiation sites. The TCD was employed to predict the fatigue life of two types of specimens with different notch sizes, and the results indicate that TCD provides a high prediction accuracy. The present results provide a reliable fatigue database for the assessment of domestic Zr‐2.5Nb pressure tube materials and support the applicability of TCD‐based design methodologies in nuclear engineering components. Summary: HCF behavior of Zr‐2.5Nb alloy with varying notch radii was systematically investigated.TCD effectively predicts the fatigue life of notched Zr‐2.5Nb alloy.Notch geometry drives initiation, whereas α/β microstructure induces crack deflection. [ABSTRACT FROM AUTHOR]
Copyright of Fatigue & Fracture of Engineering Materials & Structures is the property of Wiley-Blackwell and its content may not be copied or emailed to multiple sites without the copyright holder's express written permission. Additionally, content may not be used with any artificial intelligence tools or machine learning technologies. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
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DbLabel: Engineering Source
An: 195038585
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  Label: Title
  Group: Ti
  Data: Investigation on the High‐Cycle Fatigue Behavior of Domestic Zr‐2.5Nb Alloy in Consideration of Notch Effects.
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  Data: <searchLink fieldCode="AR" term="%22Ding%2C+Wenjing%22">Ding, Wenjing</searchLink><relatesTo>1</relatesTo> (AUTHOR)<br /><searchLink fieldCode="AR" term="%22Bao%2C+Chen%22">Bao, Chen</searchLink><relatesTo>1</relatesTo> (AUTHOR)<i> bchxx@163.com</i>
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  Data: <searchLink fieldCode="JN" term="%22Fatigue+%26+Fracture+of+Engineering+Materials+%26+Structures%22">Fatigue & Fracture of Engineering Materials & Structures</searchLink>. Aug2026, Vol. 49 Issue 8, p3252-3262. 11p.
– Name: Subject
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  Data: <searchLink fieldCode="DE" term="%22Notch+effect%22">Notch effect</searchLink><br /><searchLink fieldCode="DE" term="%22High+cycle+fatigue%22">High cycle fatigue</searchLink><br /><searchLink fieldCode="DE" term="%22Microstructure%22">Microstructure</searchLink><br /><searchLink fieldCode="DE" term="%22Fatigue+life%22">Fatigue life</searchLink><br /><searchLink fieldCode="DE" term="%22Zirconium+alloys%22">Zirconium alloys</searchLink><br /><searchLink fieldCode="DE" term="%22Nuclear+reactor+materials%22">Nuclear reactor materials</searchLink><br /><searchLink fieldCode="DE" term="%22Crack+propagation%22">Crack propagation</searchLink>
– Name: Abstract
  Label: Abstract
  Group: Ab
  Data: The Zr‐2.5Nb alloy used for pressure tubes in heavy‐water reactors was utilized to investigate its high‐cycle fatigue (HCF) behavior at room temperature using both smooth and notched specimens. Based on the Theory of Critical Distance (TCD), the influence of notch geometry on fatigue behavior and life prediction was systematically examined. The fatigue failure mechanisms were further elucidated through micrographic observation. The results indicate that the main factors of fatigue life differ substantially between smooth and notched specimens, as well as crack initiation and propagation characteristics. For Zr‐2.5Nb with smaller grain sizes, typical spalling‐like stepped morphologies are observed on the fracture surface under high stress levels. Stress concentration significantly affects both the number and distribution of fatigue crack initiation sites. The TCD was employed to predict the fatigue life of two types of specimens with different notch sizes, and the results indicate that TCD provides a high prediction accuracy. The present results provide a reliable fatigue database for the assessment of domestic Zr‐2.5Nb pressure tube materials and support the applicability of TCD‐based design methodologies in nuclear engineering components. Summary: HCF behavior of Zr‐2.5Nb alloy with varying notch radii was systematically investigated.TCD effectively predicts the fatigue life of notched Zr‐2.5Nb alloy.Notch geometry drives initiation, whereas α/β microstructure induces crack deflection. [ABSTRACT FROM AUTHOR]
– Name: AbstractSuppliedCopyright
  Label:
  Group: Ab
  Data: <i>Copyright of Fatigue & Fracture of Engineering Materials & Structures is the property of Wiley-Blackwell and its content may not be copied or emailed to multiple sites without the copyright holder's express written permission. Additionally, content may not be used with any artificial intelligence tools or machine learning technologies. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract.</i> (Copyright applies to all Abstracts.)
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RecordInfo BibRecord:
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    Identifiers:
      – Type: doi
        Value: 10.1111/ffe.70314
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      – Code: eng
        Text: English
    PhysicalDescription:
      Pagination:
        PageCount: 11
        StartPage: 3252
    Subjects:
      – SubjectFull: Notch effect
        Type: general
      – SubjectFull: High cycle fatigue
        Type: general
      – SubjectFull: Microstructure
        Type: general
      – SubjectFull: Fatigue life
        Type: general
      – SubjectFull: Zirconium alloys
        Type: general
      – SubjectFull: Nuclear reactor materials
        Type: general
      – SubjectFull: Crack propagation
        Type: general
    Titles:
      – TitleFull: Investigation on the High‐Cycle Fatigue Behavior of Domestic Zr‐2.5Nb Alloy in Consideration of Notch Effects.
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            NameFull: Ding, Wenjing
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            NameFull: Bao, Chen
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            – D: 01
              M: 08
              Text: Aug2026
              Type: published
              Y: 2026
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              Value: 49
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              Value: 8
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            – TitleFull: Fatigue & Fracture of Engineering Materials & Structures
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