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Multiphysics Design And Sensitivity Analysis Of Nuclear Heated Critical Heat Flux Pool Boiling Test Devices In Treat., Richard Hernandez
Multiphysics Design And Sensitivity Analysis Of Nuclear Heated Critical Heat Flux Pool Boiling Test Devices In Treat., Richard Hernandez
Doctoral Dissertations
Following the events of the 2011 Fukushima Daiichi accident, there has been a drive to develop accident tolerant fuels (ATF) capable of enhancing safety margins provided by conventional light water reactor (LWR) materials, with a focus on the critical heat flux (CHF) behavior under fast transient heating irradiation conditions. Presented in this dissertation, is the modeling scope of a current effort aimed at elucidating the mechanisms of CHF under in-pile fast transient irradiation conditions using the Transient Reactor Test (TREAT) facility. A heater rodlet made from stainless steel type-304 with tailored natural boron content was held within experimental pool boiling …