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Applicability of 3 mm Reduced-Thickness Miniature C(T) Specimens for Fracture Toughness Characterization of Nuclear Reactor Materials

  • Aalto University

Research output: Contribution to journalArticleScientificpeer-review

Abstract

Enhancement of fracture mechanics small-scale specimen test techniques is important, especially in the nuclear industry for the safe lifetime extension of power plants. Miniature-sized test specimens enable more efficient use of the reducing amount of reactor pressure vessel surveillance reference materials. This paper studies the limits of specimen miniaturization by means of fracture mechanics testing and determination of reference temperature T0, supported by microstructural characterization, particle analysis, and Finite Element Modelling (FEM). Tests indicate the same reference temperature T0, −102°C, for both the 4 mm and 3 mm thick specimens investigated. Particle distribution analysis showed a statistically sufficient amount of initiating particles in the cross-section of the 3 mm thick specimen. FEM results including comparative analysis of four different specimen thicknesses showed similar stress and strain states in the 3 mm and 4 mm thick specimens. Maximum stress site versus crack initiation location is discussed, as well as the adaptability of ASTM standard E1921 and weakest-link theory regarding the applicability of miniature compact tension specimens with reduced thickness.
Original languageEnglish
Article number156713
JournalJournal of Nuclear Materials
DOIs
Publication statusAccepted/In press - 1 May 2026
MoE publication typeA1 Journal article-refereed

Funding

This work was supported by Finnish Nuclear Power Plant Safety Programme SAFIR2022 as part of the AMOS (Advanced Materials Characterization for Structural Integrity Assessment) project and National Nuclear Safety and Waste Management Research Programme SAFER2028 as part of the CHAOS (Characterization of NPP Structural Integrity) project, which is gratefully acknowledged.

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