Fuel development for reduced enrichment research and test reactor (RERTR) program is tasked with the development of new low enrichment uranium fuels that can be employed to replace existing high enrichment uranium fuels currently used in many research and test reactors worldwide. Radiation stability of the interaction product formed at fuel-matrix interface has a strong impact on fuel performance. Three depleted uranium alloys are cast that consist of the following 5 phases of interest to be investigated: U(Si,Al)3, (U,Mo)(Si,Al)3, UMo2Al20, U6Mo4Al43 and UAl4. Irradiation of TEM disc samples with 500 keV Kr ions at 200?C to high doses up to ~100 dpa were conducted using an intermediate voltage electron microscope equipped with an ion accel...
The paper summarizes the irradiation test and post-irradiation examination (PIE) data for the U-Mo l...
Uranium-molybdenum (U-Mo) is a metallic fuel studied for decades for use in research and test reac...
During the exploitation of nuclear reactors, various U-Al based ternary intermetallides are formed i...
A variety of phases have the potential to develop in the irradiated fuels for the reduced enrichment...
Three depleted uranium alloys are successfully cast for the radiation stability studies of the fuel-...
The recent development on TEM work of irradiated RERTR fuels includes microstructural characterizati...
Twelve uranium alloys have been selected for incorporation into very high density aluminum dispersio...
The silicide dispersion fuel of U3Si2/Al has been recognized as a reasonably good performance fuel f...
Uranium-zirconium alloys are being investigated for use in metallic inert matrix nuclear fuels (IMF)...
Understanding the microstructural and phase changes occurring during irradiation and their impact on...
Since 2001, a series of five irradiation test campaigns for atomized U-Mo dispersion fuel rods, KOMO...
Ion-beam irradiation has been conducted to demonstrate and assess solid phase dependence of fission ...
The RERTR-3 irradiation test was designed to investigate the irradiation behavior of aluminum matrix...
Microstructural characterization of irradiated dispersion and monolithic RERTR fuel plates using sca...
Uranium-zirconium alloys are being investigated for use in ultrahigh burn-up, metallic inert matrix ...
The paper summarizes the irradiation test and post-irradiation examination (PIE) data for the U-Mo l...
Uranium-molybdenum (U-Mo) is a metallic fuel studied for decades for use in research and test reac...
During the exploitation of nuclear reactors, various U-Al based ternary intermetallides are formed i...
A variety of phases have the potential to develop in the irradiated fuels for the reduced enrichment...
Three depleted uranium alloys are successfully cast for the radiation stability studies of the fuel-...
The recent development on TEM work of irradiated RERTR fuels includes microstructural characterizati...
Twelve uranium alloys have been selected for incorporation into very high density aluminum dispersio...
The silicide dispersion fuel of U3Si2/Al has been recognized as a reasonably good performance fuel f...
Uranium-zirconium alloys are being investigated for use in metallic inert matrix nuclear fuels (IMF)...
Understanding the microstructural and phase changes occurring during irradiation and their impact on...
Since 2001, a series of five irradiation test campaigns for atomized U-Mo dispersion fuel rods, KOMO...
Ion-beam irradiation has been conducted to demonstrate and assess solid phase dependence of fission ...
The RERTR-3 irradiation test was designed to investigate the irradiation behavior of aluminum matrix...
Microstructural characterization of irradiated dispersion and monolithic RERTR fuel plates using sca...
Uranium-zirconium alloys are being investigated for use in ultrahigh burn-up, metallic inert matrix ...
The paper summarizes the irradiation test and post-irradiation examination (PIE) data for the U-Mo l...
Uranium-molybdenum (U-Mo) is a metallic fuel studied for decades for use in research and test reac...
During the exploitation of nuclear reactors, various U-Al based ternary intermetallides are formed i...