Detailed measurements of local thickness changes for U-7Mo dispersion fuel plates with Al-3.5Si matrix after irradiation at different powers in the RERTR-9B experiment
Sign Up to like & getrecommendations! Published in 2017 at "Journal of Nuclear Materials"
DOI: 10.1016/j.jnucmat.2017.07.047
Abstract: Abstract The Materials Management and Minimization program is developing fuel designs to replace highly enriched fuel with fuels of low enrichment. Swelling is an important irradiation behavior that needs to be well understood. Data from… read more here.
Keywords: 7mo dispersion; power; fuel; dispersion fuel ... See more keywords
Thermal creep effects of aluminum alloy cladding on the irradiation-induced mechanical behavior in U–10Mo/Al monolithic fuel plates
Sign Up to like & getrecommendations! Published in 2020 at "Nuclear Engineering and Technology"
DOI: 10.1016/j.net.2019.09.008
Abstract: Abstract Three-dimensional finite element simulations are implemented for the in-pile thermo-mechanical behavior in U–Mo/Al monolithic fuel plates with different thermal creep rates of cladding involved. The numerical results indicate that the thickness increment of fuel… read more here.
Keywords: fuel foil; monolithic fuel; thermal creep; creep coefficient ... See more keywords
Relating Diffusion Couple Experiment Results to Observed As-Fabricated Microstructures in Low-Enriched U-10wt.% Mo Monolithic Fuel Plates
Sign Up to like & getrecommendations! Published in 2017 at "Defect and Diffusion Forum"
DOI: 10.4028/www.scientific.net/ddf.375.18
Abstract: Monolithic fuel system with U – 10 wt.% Mo (U10Mo) fuel alloy has been developed for the Materials Management and Minimization reactor conversion program to replace highly-enriched fuels in research and test reactors with low-enriched… read more here.
Keywords: diffusion; system; monolithic fuel; low enriched ... See more keywords