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Transmission electron microscopy of ion irradiated ODS MA956 samples
Oxide dispersion strengthened (ODS) alloys are promising candidate materials for the next generation advanced nuclear reactors due to their superior irradiation resistance and... -
TEM Characterization of Neutron Irradiated HfAl3-Al Composite Specimens
Particles comprised of a thermal neutron absorbing material (HfAl3) are dispersed in a metal matrix material with high thermal conductivity (aluminum) to conduct the heat... -
2024 NSUF User Development Workshop on Irradiation Testing
Monday, May 20 – Thursday, May 23, 2024 at Center for Advanced Energy Studies at Idaho National Laboratory, Idaho Falls, Idaho. This pilot workshop was hosted to expand the NSUF... -
Atom probe datasets from neutron irradiated Fe-Cr alloys
A series of model Fe–Cr alloys containing 3–18 at.% Cr was neutron irradiated at a nominal temperature of 563 K to 1.82 dpa. Solute distributions were analyzed by atom probe... -
2025 NSUF Users Organization Annual Meeting
There is no description for this dataset
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2025 NSUF Foundations of Irradiation Testing: A Workshop for Researchers
There is no description for this dataset
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2024 NSUF Users Organization Annual Meeting
The 2024 Nuclear Science User Facilities Users Organization meeting was held in association with the Minerals, Metals and Materials Society (TMS) 2024 Annual Meeting and... -
2024 NSUF Annual Program Review
The Department of Energy - Office of Nuclear Energy’s (DOE-NE) Nuclear Science User Facilities (NSUF) program held its annual review on Monday, April 15 through Thursday, April...