Publications

Sep, 2026

Journal

Reactive atmosphere fabrication of nanostructured alumina-forming austenitic alloys for nuclear applications

Although advanced austenitic alloys are advantageous in non-nuclear applications due to their high creep strength, designing irradiation-resistant austenitic alloys is challenging due to the difficulty of dispersing irradiation defect-capturing sinks uniformly throughout the material. In this work, nanostructured alumina-forming austenitic (NAFA) alloys were successfully p…

Jul, 2026

Journal

Microstructure-Dependent Particulate Populations in ODS Steels Revealed by Single-Particle ICP-TOF-MS

In this work, we evaluated the ability of single-particle inductively coupled plasma time-of-flight mass spectrometry (SP-ICP-TOF-MS) to characterize particulates generated from 300 series stainless steels and oxide dispersion–strengthened (ODS) steels. Particulates were produced using two different rotary tools (cutting disk and grinding bit) to assess the influence of pa…

Apr, 2026

ORNL Report

Development and Evaluation of Embrittlement Resistant Alloys for Advanced LWR Cladding

Apr, 2026

ORNL Report

Mechanical Property Measurements of HFIR-irradiated FM and ODS Alloys

Mar, 2026

Conference Paper

Characterization of Precipitation-Strengthening Heat-Resistant Austenitic Stainless Steels for Life-Prediction Modeling

In this study, the role of minor alloying additions in 347H stainless steels (UNS34709, ASTM A240/240M) on creep-rupture properties at 650-750°C and microstructure evolution during isothermal exposure at 750°C has been investigated, aiming to provide the experimental dataset as boundary conditions of physics-based modeling for material/component life prediction. Four diffe…

Mar, 2026

Conference Paper

Distribution of Tritium in the Near Surface of Candidate Structural Materials for Fusion Reactors. Type 304L Stainless Steel, Inconel, Hastelloy, Eurofer-97, Oxide Dispersion-Strengthened Alloy 14YWT

Five different candidate structural materials for fusion have undergone pure tritium gas soaking at room temperature and at 310-mbar(a) pressure. The tritium uptake on the surface and in the bulk of the alloys has been analyzed using surface leaching, chemical etching, and thermal desorption. The nickel-based alloys: Inconel-X-750 and Hastelloy-X, absorbed the least amount…

Aug, 2025

ORNL Report

Nanostructured Alumina Forming Austenitic Alloy (NAFA) Production using Advanced Manufacturing

Jul, 2025

ORNL Report

Production of Creep-Resistant FeCrAl-ODS

Mar, 2025

Journal

In situ self-ion (Fe+) irradiation of ODS-FeCrAl alloy fuel cladding materials with different Cr contents: The early stages of Cr-rich α’ phase precipitation

Oxide-dispersion-strengthened FeCrAl (ODS-FeCrAl) alloys are candidate accident-tolerant fuel cladding materials for light water reactors because they demonstrate satisfactory resistance to materials degradation effects such as high-temperature oxidation, radiation-induced swelling, and creep. Their perspective deployment to market is challenged, however, by their inherent…

Sep, 2024

ORNL Report

Report Summarizing the Mechanical Properties of a Large ODS Ferritic Alloy Ingot by Forging at High Temperatures for Future Mother Tube Production

Sep, 2024

ORNL Report

Nanostructured Alumina Forming Austenitic Alloy (NAFA) production using mechanical alloying and high-temperature consolidation

Sep, 2024

ORNL Report

Characterization of Large Batch 14YWT Heat (NFA-2) for JOYO Irradiations