Work

Atomistic study of radiation-induced ductile-to-brittle transition in austenitic steel

Year: 2025

Type: article

Abstract: Neutron irradiation in structural alloys promotes defect clustering, which suppresses plasticity and triggers a ductile-to-brittle transition (DBT), a key degradation mechanism limiting fracture resistance in nuclear materials. This study investigates the fracture mechanisms underlying this transition in irradiated Fe–Ni–Cr alloys. Using Molecular Dynamics simulations, we examine how different defect types influence crack propagation and energy dissipation mechanisms. The results reveal distinct roles of these defects: voids facilitate crack growth by reducing local cohesive energy, while dislocation loops act as barriers that impede crack advancement and redirect crack paths, significantly altering crack morphology. Building on the classical approach of separating fracture energy into brittle cleavage and plastic components, this study adapts the decomposition to irradiated materials. This framework quantifies the evolving contributions of surface energy and plastic work across increasing radiation damage levels, providing critical insight into how irradiation-induced defects govern fracture dynamics.

Source: International Journal of Mechanical Sciences

DOI: 10.1016/j.ijmecsci.2025.110567

Authors: A. Ustrzycka, H. Mousavi, F.J. Dominguez-Gutierrez, S. Stupkiewicz

Institutions: Institute of Fundamental Technological Research, Polish Academy of Sciences, National Centre for Nuclear Research

Language: English

Topic: Fusion materials and technologies

Subfield: Materials Chemistry

Field: Materials Science

Domain: Physical Sciences

Open Access status: hybrid

Estimated APC paid: $4,740

Funders: Fundacja na rzecz Nauki Polskiej, Narodowe Centrum Nauki, Horizon 2020 Framework Programme, European Regional Development Fund