The fracture behavior of nuclear grade graphites is strongly influenced by underlying
microstructural features such as the character of filler particles, and the distribution of pores …

U-Mo alloys irradiated with 84 MeV Xe ions to various doses were characterized with
transmission electron microscopy (TEM) and scanning transmission electron microscopy …

Here synchrotron scattering analysis results on U–7wt.% Mo fuel specimens irradiated in the
Advanced Test Reactor to three burnup levels (3.0, 5.2, and 6.3× 10 21 fission/cm 3) are …

Abstract The combination of MeV/Nucleon ion irradiation (eg 133 MeV Xe) and high energy
synchrotron x-ray characterization (eg at the Argonne Advanced Photon Source, APS) …

This study investigates the irradiation behavior of U-7Mo fuels, examining matrix effects,
fission gas pore (FGP) morphology, and uranium carbide (UC) inclusions. Comparisons …

Approximately 250 research and test reactors are used for materials research, education
and training, neutron scattering, isotope production, and materials research in 55 countries …

Several existing ion irradiation facilities in the US are being used for accelerated testing of
materials to support the DOE-NE mission related to investigation of nuclear materials …

The effectiveness of a transition metal coating layer as a diffusion barrier between the UMo
and matrix Al was examined. The samples were cut from KAERI-made U–Mo/Al dispersion …

High-performance research reactors require fuel that operates at high specific power and
can withstand high fission density, but at relatively low temperatures. The design of the …

The microstructure evolution and phase transformation of the interdiffusion layer resulting
from the interaction between U–Mo and Al in U–Mo/Al bilayer systems irradiated from 140° …