Publications

Sep, 2026

Journal

A comparison of wrought and powder metallurgical FeCrAl claddings under simulated LWR accident transients

Iron-chromium-aluminum (FeCrAl) alloys are potential accident tolerant fuel (ATF) cladding candidates for light-water reactors but are difficult to fabricate as thin-walled tubes via conventional cast-and-wrought routes. Powder metallurgy (PM) offers a manufacturing alternative with improved compositional control, but its transient accident performance has not been directl…

Aug, 2026

ORNL Report

Automated 4D X-ray Computed Tomography Registration and Flaw Tracking Across Interrupted Creep Testing of Additively Manufactured Steel

Aug, 2026

ORNL Report

Additively Manufactured Components for Nuclear Power Applications

The AMMT work package for fiscal year 2026 entitled Component Manufacturing and Demonstrations from AM 316 SS includes three activities that showcases qualities of AM 316 SS that are relevant to the domestic nuclear power sector. The design and fabrication of capsules for INL provide a basis for studying the complexities of interaction of AM 316H SS with salt used in molte…

Jul, 2026

ORNL Report

Irradiation of Advanced Cladding Specimens in the High Flux Isotope Reactor: Capsule Designs and Test Matrix

Jun, 2026

ORNL Report

ORNL–TERRAPOWER SEMIANNUAL PROGRESS REPORT: PROGRAM STATUS THROUGH APRIL 2026

Jun, 2026

ORNL Report

Summary of the Initial Post-Irradiation Characterization of HFIR-Irradiated Low-N and High-N HT-9 Steel

May, 2026

ORNL Report

AMMT Round Robin 316H HFIR Irradiation Test Matrix and Readiness for Insertion

May, 2026

ORNL Report

Shipment of Specimens to JAEA for JOYO irradiation

Apr, 2026

ORNL Report

Development of Large Bore Rabbit Capsules in Support of BWR Cladding Irradiations in HFIR

Apr, 2026

ORNL Report

Development and Evaluation of Embrittlement Resistant Alloys for Advanced LWR Cladding

Apr, 2026

ORNL Report

AFC Time-at-Temperature Irradiation Campaign and Post-Irradiation Examination Plan

Apr, 2026

ORNL Report

Report on Preliminary Detailed Experimental Plan for Neutron Irradiation of A709 at ATR and HFIR

Advanced nuclear power technologies will use higher temperatures as a means to extract energy at a higher efficiency than current plants and therefore put a larger demand on the structural materials. Improved performance of structural materials could enable greater safety margins, longer plant lifetimes, and reduce maintenance costs. Alloy 709 is championed as the next gen…