Assessment of deformation mechanisms in neutron-irradiated accident-tolerant fecral alloys via in situ mechanical testing and TEM analysis

Iron-chromium-aluminum (FeCrAl) alloys are promising as an accident-tolerant fuel cladding for loss-of-coolant accident scenarios; however, limited data are available on the acting deformation mechanisms for this class of materials after neutron …

Hydrothermal corrosion of coatings on silicon carbide in boiling water reactor conditions

SiC/SiC ceramic matrix composites are an attractive material for use as accident tolerant fuel cladding. However, despite its resistance to corrosion in high-temperature steam, SiC is known to dissolve in high-temperature water, necessitating the use …

Post-Irradiation Fracture Toughness Characterization of Generation II FeCrAl Alloys

Accelerated irradiation testing of miniature fuel specimens

Design and Thermal Analysis for Irradiation of Tensile Specimens from Wrought, Powder Metallurgy, and Additive Processed Alloys in the HFIR

Ex-situ and in-situ determination of alpha prime phase formation/dissolution in high-cr ferritic alloys using small-angle neutron scattering.

Handbook on the Material Properties of FeCrAl Alloys for Nuclear Power Production Applications (FY18 Version: Revision 1.1) Prepared for U.S. Department of Energy Nuclear Technology R\&D Advanced Fuels Campaign FY18 version author(s): Kevin G. Field 1 FY17 version author(s)

High Temperature Mechanical Properties of HFIR Irradiated FeCrAl Alloys

Multi-modal STEM-based tomography of HT-9 irradiated in FFTF

Preliminary Characterization and Mechanical Performance of Additively Manufactured HT9

Laser-blown powder deposition of HT9 was performed to evaluate the feasibility of using advanced manufacturing to fabricate creep strength enhanced ferritic steels. The as-printed materials were tensile tested at room temperature, 330�C, and 550�C to …