SinoTechIntel Academic Portal
Open AccessDOI: 10.1007/s12613-024-3043-0Original Research

In-situ research on tensile deformation and microvoid formation in a nuclear pressure vessel steel

Zhifeng Zhang¹,Daming Tong¹,Xingyun Yang¹,Xiaofang Wang¹,Lizhan Han¹,Guanghua Yan¹,Chuanwei Li¹,Jianfeng Gu¹

Shanghai Jiao Tong University

Read Executive PreviewQuick FAQ
In-situ research on tensile deformation and microvoid formation in a nuclear pressure vessel steel
Graphical Abstract / Figure
Published In
Int. Journal of Minerals, Metallurgy and Materials (矿物冶金与材料学报)
Published:January 15, 2025Edition:Vol. 32, Issue 8 • pp. 1893-1902Citation:Zhifeng Zhang et al. (2025), Int. Journal of Minerals, Metallurgy and Materials (矿物冶金与材料学报)
Sponsored Research Partner
Keywords & Index Terms:nuclear pressure vessel steelSA508 Gr.3tensile deformationin-situ EBSDdigital image correlationductile fracturebainite

Key Takeaways & Executive Findings

  • • In-situ DIC and EBSD reveal distinct microvoid initiation mechanisms in quenched vs. tempered SA508 Gr.3 steel, linking microstructure to ductile fracture. • Tempering reduces UTS but significantly enhances ductility, with local strain reaching 191% at necking, due to carbide morphology changes. • Microvoids initiate via PAGB decohesion at M-A islands in quenched steel, but via carbide fracture and PAGB decohesion in tempered steel. • Both conditions exhibit ductile dimple fracture, confirming microvoid coalescence as the dominant failure mode, critical for nuclear pressure vessel reliability.
Sponsored Research Highlight

Abstract

Tensile deformation and microvoid formation of quenched and tempered SA508 Gr.3 steel were studied using an in-situ digital image correlation technique and in-situ electron backscatter diffraction (EBSD) measurements. The quenched steel with a mixture of upper bainite and granular bainite exhibited a high ultimate tensile strength (UTS) of ~795 MPa and an elongation of ~25%. After tempering, long-rod carbides and accumulated carbide particles were formed at the interface of bainite–ferrite subunits and prior austenite grain boundaries (PAGBs), respectively. The UTS of the tempered steel decreased to ~607 MPa, whereas the total elongation increased to 33.0% with a local strain of 191.0% at the necked area. In-situ EBSD results showed that strain localization in the bainite–ferrite produced lattice rotation and dislocation pileup, thus leading to stress concentration at the discontinuities (e.g., martensite–austenite islands and carbides). Consequently, the decohesion of PAGBs dotted with martensite–austenite islands was the dominant microvoid initiation mechanism in the quenched steel, whereas microvoids primarily initiated through the fracturing of long-rod carbides and the decohesion of PAGBs with carbides aggregation in the tempered steel. The fracture surfaces for both the quenched and tempered specimens featured dimples, indicating the ductile failure mechanism caused by microvoid coalescence.

1. Introduction

Over the past decades, numerous studies have focused on the development of new-generation steel for nuclear pressure vessels [1–2]. However, SA508 Gr.3 steel is still the most popular material for the fabrication of nuclear reactor pressure vessels [3–5]. The reliability of this steel is crucial to the safety of currently operating nuclear power plants. Therefore, various strategies are proposed to improve the initial properties of this steel [6–8].

Reportedly, two-step tempering can inhibit the formation of long rod-shaped carbides by inducing martensite–austenite (M–A) island decomposition at a low temperature, thus obtaining superior ductility and toughness [7]. Nevertheless, the role of microstructures commonly found in this steel, such as bainite, M–A islands, and carbides, in the deformation damage has rarely been reported. Thus, more studies are needed to elucidate the mechanisms of ductile fracture in this steel, especially the initiation and development of microvoids and their interactions with microstructures, which are important for the reliability of nuclear power components.

Ductile fracture of metals preceded by significant plastic deformation usually involves the initiation and development of microvoids, which is strongly related to the stress state [9–10]. Microvoids generally nucleate around stress concentrators, which are discontinuities present in the structure of materials, such as second-phase particles and crystal defects. Subsequently, the plastic strain of the surrounding matrix promotes the growth of microvoids. Second-phase particles distributed on grain boundaries or inside grains are generally considered to be the initiators of microvoids because of the localized plastic strain and the heterogeneity in the strain field around these particles.

SinoTechIntel Interactive Document Reader
Page 1–5 of Preview
100%
Download Full PDF

Loading authentic research manuscript (Pages 1–5)...

Sponsored Research Partner
Cite This Research Paper
Zhifeng Zhang, Daming Tong, Xingyun Yang, Xiaofang Wang, Lizhan Han, Guanghua Yan, Chuanwei Li, Jianfeng Gu (2025). In-situ research on tensile deformation and microvoid formation in a nuclear pressure vessel steel. Int. Journal of Minerals, Metallurgy and Materials (矿物冶金与材料学报). https://doi.org/10.1007/s12613-024-3043-0
SinoTechIntel Academic & Legal Disclaimer

Research & Educational Purpose Only:The translations, structured abstracts, analytical annotations, and data reports provided by SinoTechIntel are intended exclusively for academic research, internal corporate R&D, and educational benchmarking. They do not constitute formal engineering, chemical safety, legal, or professional advice.

Copyright & Intellectual Property Notice: Original copyright of the underlying source articles and experimental data remains with the respective authors, institutions, and original publishing journals. SinoTechIntel claims intellectual property only over its proprietary translations, analytical syntheses, and AEO structured enhancements in accordance with international fair use and academic citation principles.

Frequently Asked Questions

What is the main objective of this study?

The study aims to investigate the tensile deformation and microvoid formation mechanisms in SA508 Gr.3 nuclear pressure vessel steel using in-situ digital image correlation and EBSD techniques, correlating microstructural features with ductile fracture behavior.

How does tempering affect the mechanical properties of SA508 Gr.3 steel?

Tempering reduces the ultimate tensile strength from ~795 MPa to ~607 MPa but increases total elongation from ~25% to 33.0%, with a local strain of 191.0% at the necked area, indicating improved ductility.

What are the dominant microvoid initiation mechanisms in quenched and tempered conditions?

In quenched steel, microvoids initiate primarily by decohesion of prior austenite grain boundaries decorated with martensite-austenite islands. In tempered steel, microvoids initiate through fracturing of long-rod carbides and decohesion of PAGBs with carbide aggregation.

What is the significance of in-situ EBSD in this research?

In-situ EBSD allows real-time observation of strain localization, lattice rotation, and dislocation pileup, providing direct evidence of stress concentration at microstructural discontinuities, which is crucial for understanding microvoid nucleation.

What are the practical implications of this study for nuclear pressure vessel reliability?

By elucidating the microvoid initiation mechanisms, the study provides insights for optimizing heat treatment processes to enhance ductility and toughness, thereby improving the safety and reliability of nuclear pressure vessels.

Recommended Scientific Literature & Research Partners

Related Technical Papers & Translations

Research Paper
Direct Repair of the Crystal Structure and Coating Surface of Spent LiFePO4 Materials Enables Superfast Li-Ion Migration

Direct Repair of the Crystal Structure and Coating Surface of Spent LiFePO4 Materials Enables Superfast Li-Ion Migration

The rapid accumulation of spent LiFePO4 (LFP) cathodes from retired lithium-ion batteries necessitates the development of effective and environmental-friendly recycling strategies. In this context, direct regeneration has emerged as a promising approach for reclaiming LFP cathode materials, offering a streamlined pathway to restore their electrochemical functionality. We report an integrated regeneration protocol that simultaneously repairs the degraded crystal structure and reconstructs the damaged carbon coating in spent LFP. The regenerated cathode material had superfast lithium-ion diffusion kinetics and a stable cathode–electrolyte interface, giving a remarkable rate capability with specific capacities of 122 mAh g−1 at 5C and 106 mAh g−1 at 10C (1C = 170 mA g−1). It also maintained capacities of 110.7 mAh g−1 (5C) and 84.1 mAh g−1 (10C) after 400 cycles. It could be used in harsh environments and could be stably cycled at subzero temperatures (−10 and −20 °C) and in solid-state electrolyte batteries. Life cycle assessment combined with economic evaluation using the EverBatt model reveals that this direct regeneration approach has high economic and environmental benefits.

Read Abstract & PDF
Research Paper
Oxide Semiconductor for Advanced Memory Architectures: Atomic Layer Deposition, Key Requirement and Challenges

Oxide Semiconductor for Advanced Memory Architectures: Atomic Layer Deposition, Key Requirement and Challenges

Oxide semiconductors (OSs), introduced by the Hosono group in the early 2000s, have evolved from display backplane materials to promising candidates for advanced memory and logic devices. The exceptionally low leakage current of OSs and compatibility with three-dimensional (3D) architectures have recently sparked renewed interest in their use in semiconductor applications. This review begins by exploring the unique material properties of OSs, which fundamentally originate from their distinct electronic band structure. Subsequently, we focus on atomic layer deposition (ALD), a core technique for growing excellent OS films, covering both basic and advanced processes compatible with 3D scaling. The basic surface reaction mechanisms—adsorption and reaction—and their roles in film growth are introduced. Furthermore, material design strategies, such as cation selection, crystallinity control, anion doping, and heterostructure engineering, are discussed. We also highlight challenges in memory applications, including contact resistance, hydrogen instability, and lack of p-type materials, and discuss the feasibility of ALD-grown OSs as potential solutions. Lastly, we provide an outlook on the role of ALD-grown OSs in memory technologies. This review bridges material fundamentals and device-level requirements, offering a comprehensive perspective on the potential of ALD-driven OSs for next-generation semiconductor memory devices.

Read Abstract & PDF
Research Paper
Laser powder bed fusion of biodegradable Zn-4Cu alloy: Processing, microstructure and properties

Laser powder bed fusion of biodegradable Zn-4Cu alloy: Processing, microstructure and properties

Zn's natural degradability and biocompatibility make it a promising candidate for implants, however, its mechanical properties remain insufficient for bone applications. In this study, the performance of Zn was enhanced by developing Zn-Cu alloys via laser powder bed fusion (LPBF). Optimal LPBF parameters for forming stable tracks were achieved by adjusting laser power and scanning speed. Under optimized conditions of 100 W and 100 mm/s, high-density (99.58%) Zn-Cu alloys with improved hardness (68.2HV) and yield strength (160 MPa) were achieved. These improvements are attributed to solid solution strengthening, segregation strengthening, and grain refinement. The Zn-Cu alloys also demonstrated favorable degradation behavior, with a rate of 0.16 mm/year. This degradation is primarily driven by micro-galvanic corrosion between the CuZn5 phase and Zn matrix, along with refined grains and increased grain boundary density. This work demonstrates a viable strategy for fabricating Zn-based implants with enhanced structural integrity and mechanical performance via LPBF.

Read Abstract & PDF