1 Bethel Valley Road, P.O. Box 2008, Mail Stop 608
Room B-106, Building 5700
Oak Ridge, TN 37831
United States
Government of the United States of America - Oak Ridge National Laboratory
tungsten, grain boundaries, transport properties, ebsd, Neutron irradiation
high temperature, steel, ion irradiation, helium irradiation, dual ion irradiation, phase stability, nuclear materials, fusion materials, characterization, TEM, MX precipitates
steel, Creep, Precipitate quantification, Laves phases, Electron microscopy
yttrium hydride, neutron irradiation, post-irradiation examination, cavity formation, irradiation-induced defects, electron microscopy
Sintered Nanostructured Alloy, Direct Current Sintering, Creep, Nanoindentation, Stress exponent
steel, swelling, dual ion irradiation, helium, phase stability, MX precipitates