Publications
Showing 159 results for Author: Maxim N. Gussev
Apr, 2026
Journal
Mechanical properties, strain hardening, and fracture behavior of ultrasonic additively manufactured Zircaloy-4 after low-temperature neutron irradiation
Ultrasonic additive manufacturing (UAM) is a solid-state, layer-by-layer advanced manufacturing process that has the potential to create custom spatially controlled composites with embedded wires and sensors for nuclear component manufacture. To assess the feasibility of using UAM for nuclear-relevant materials research, the technique was used to produce a 3.5-mm-thick Zir…
Apr, 2026
Journal
Emerging hierarchical dislocation structures: Insights from scanning electron microscopy-electron backscatter diffraction in situ tensile testing and multifractal analysis
Understanding the evolution of dislocation structures during plastic deformation is critical for predicting the mechanical performance of metallic materials. In this work, we applied in situ scanning electron microscopy/electron backscatter diffraction tensile testing combined with multifractal (MF) analysis to assess deformation-induced dislocation structure evolution in…
Mar, 2026
Conference Paper
Plastic Deformation Processes Accompanying Stress Corrosion Crack Propagation in Irradiated Austenitic Steels
During stress corrosion crack propagation, stress values in the crack tip vicinity often exceed material yield stress limit. Plastic deformation processes may accompany and influence cracking. Here, stress corrosion crack propagation and deformation mechanisms were investigated using EBSD analysis. The investigated material was 304L Ti-enriched austenitic stainless steel i…
Mar, 2026
Conference Paper
MECHANICAL BEHAVIOR OF FRESH, HYDRIDED, AND Cr-COATED CLADDING TUBES AND SUB-SIZED FLAT SPECIMENS
Feb, 2026
ORNL Report
Neutron Diffraction Residual Stress Characterization of Large-Scale Components by WA-DED
Two large scale 316L stainless steel cylindrical shells were fabricated by wire arc directed energy deposition (WA DED). Residual stresses were measured by neutron diffraction, and the microstructure and mechanical properties of the printed material were characterized. Longitudinal and transverse residual stresses were compressive at the inner diameter, near neutral at mid…
Oct, 2025
Journal
Study of hydride reorientation and ductility of SRA ZIRLO and PRXA ZIRLO using ring compression testing (RCT)
Before dry storage, spent nuclear fuel is dried at high temperatures, which induces hydride dissolution. Radial hydride particles precipitate when cooled under a stress above a threshold stress. This process can severely degrade the ductility of cladding tubes. Zirconium alloys with different microstructures, such as grain boundary density, were quantified and studied to e…
Sep, 2025
ORNL Report
Preparation and Analysis of Austenitic Steel Samples Irradiated at Very High Damage Doses
This report describes the preliminary results of the visual inspection, cutting, preparation for IASCC (irradiation-assisted stress corrosion cracking) testing, and property evaluation of austenitic stainless steel specimens irradiated at very-high-damage doses (up to 125 dpa) in the BOR-60 fast reactor. Work was performed at Oak Ridge National Laboratory using the Irradia…
Sep, 2025
ORNL Report
Localized Deformation Investigation in Irradiated Materials via Electron Microscopy, EBSD, and In-Situ Mechanical Testing
This report describes the preliminary results of an analysis of dislocation defect structures in nondeformed and deformed austenitic stainless steels – materials of light water reactor internal components. The analysis was performed using an advanced modern approach: high-resolution electron backscatter diffraction (HR-EBSD). Work was performed at Oak Ridge National Labora…
Sep, 2025
ORNL Report
TEM specimen manufacturing to support the analysis of IASCC mechanisms in irradiated austenitic steels – light-water relevant materials
The present report describes the manufacturing of samples for advanced microstructure studies of mechanisms of irradiation-assisted stress corrosion cracking (IASCC) in the materials of light-water reactor (LWR) internal components. The samples were manufactured via FIB (focused ion beam milling) from 4-point-bend specimens subjected to oxidation and mechanical loading in…