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Grain-scale deformation and fracture mechanisms in tempered nuclear weld metals revealed by in-situ SEM and crystal plasticity modeling

  • Lanzhou University of Technology

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Abstract

The structural integrity of nuclear reactor pressure vessel (RPV) weld metal is paramount for nuclear power plant safety. In this study, a nuclear-grade low-alloy weld-deposited metal was tempered at 615 °C for different durations, and its microstructural evolution, local deformation behavior, and fracture mechanism were investigated using SEM, EBSD, TEM, in-situ SEM tensile testing, DIC, and EBSD-based CPFEM. The as-welded (AW) condition contained martensite–austenite (M–A) islands, with a retained austenite fraction of approximately 4.4%. After tempering for 1 h, the retained austenite fraction decreased to 0.2%, accompanied by rapid M–A decomposition, nanoscale M3C precipitation, increased dislocation density, and enhanced bainitic ferrite (BF) constraint. Prolonged tempering for 20 h eliminated M–A islands but promoted ferritic matrix rebalancing, carbide coarsening, and grain-boundary localization. Tensile testing showed that the 1H condition achieved the best strength–uniform elongation balance, whereas the 20H condition exhibited significant property degradation. In-situ SEM/DIC observations and Schmid factor analysis revealed that polygonal ferrite (PF) was the primary plastic deformation carrier, while M–A islands and BF acted as less-deformable constituents that altered slip localization. CPFEM further demonstrated that cracked M–A/PF interfaces exhibited higher local strain than uncracked interfaces, indicating that interfacial strain incompatibility dominated M–A-induced crack initiation. In contrast, BF constrained plastic slip-band propagation and delayed local fracture localization in the 1H condition, whereas carbide coarsening and continuous PF grain-boundary localization accelerated microvoid coalescence in the 20H condition. These results establish a grain-scale process–structure–deformation–fracture relationship for tempered nuclear weld metals and provide guidance for optimizing post-weld tempering treatments.
Original languageEnglish
Article number150673
Pages (from-to)150673
JournalMaterials Science and Engineering: A
Volume972
Early online date25 Jun 2026
DOIs
Publication statusE-pub ahead of print - 25 Jun 2026

Funding

This research was supported by Top leading talents project of Gansu province, the Central Leading Local Science and Technology Development Special Project (No. 24ZYQA054), the Gansu Province Key R&D Plan - Industrial Projects under Grant (23YFGA0057), the National Natural Science Foundation of China (52175325), and the Major Scientific and Technological Projects of Gansu (Nos. 24ZD13GA018, 23ZDGA010, 22ZD6GA008).

FundersFunder number
Major Scientific and Technological Projects of Gansu23ZDGA010, 22ZD6GA008, 24ZD13GA018
Gansu Province Key R&D Plan - Industrial Projects23YFGA0057
National Natural Science Foundation of China52175325

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