Effects of U3Si2 fuel and minor actinide doping on fundamental neutronics, nuclear safety, and security of small and medium PWRs in comparison to conventional UO2 fuel
Sign Up to like & getrecommendations! Published in 2021 at "Annals of Nuclear Energy"
DOI: 10.1016/j.anucene.2020.108078
Abstract: Abstract Small modular reactors (SMRs) have attracted significant research interest owing to their various applications. The scale of SMRs can be adjusted according to the site. To realize the flexibility of SMRs, introduction of a… read more here.
Keywords: safety security; nuclear safety; fuel; uo2 fuel ... See more keywords
Experimentally validated Multiphysics modeling of fracture induced by thermal shocks in Sintered UO2 Pellets
Sign Up to like & getrecommendations! Published in 2022 at "Journal of Nuclear Materials"
DOI: 10.1016/j.jnucmat.2022.153719
Abstract: Commercial nuclear power plants extensively rely on fission energy from uranium dioxide (UO2) fuel pellets that provide thermal energy; consequently, generating carbon-free power in current generation reactors. UO2 fuel incurs damage and fractures during operation… read more here.
Keywords: thermal shock; fracture; fuel; uo2 pellets ... See more keywords
Coupled Monte Carlo-burnup and CFD analysis of coated UN and UC fuels in an HPLWR fuel assembly
Sign Up to like & getrecommendations! Published in 2020 at "Progress in Nuclear Energy"
DOI: 10.1016/j.pnucene.2020.103342
Abstract: Abstract Ceramic nuclear fuels may have potential benefits to be considered as nuclear fuels in future Supercritical Water Reactors (SCWR), they offer the advantage of high thermal conductivity and high-density values compared to uranium dioxide.… read more here.
Keywords: fuel assembly; analysis; monte carlo; burnup ... See more keywords
Advanced High-Temperature Sodium-Cooled Thermal Reactors Using Less Than 10% Enriched UO2 Fuel
Sign Up to like & getrecommendations! Published in 2024 at "Nuclear Science and Engineering"
DOI: 10.1080/00295639.2024.2381387
Abstract: Abstract This paper presents a 1200-MW(thermal) advanced sodium-cooled thermal reactor concept that uses online refueling of 3.5% to 9.95% enriched UO2 fuel pin bundles; uses either graphite or beryllium oxide (BeO) as a neutron moderator;… read more here.
Keywords: sodium cooled; fuel; uo2 fuel; enriched uo2 ... See more keywords