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NE 407 Nuclear Thermal-Hydraulics Laboratory
狈贰听407听听Nuclear Thermal-Hydraulics Laboratory听听(2 credit hours)听听
狈贰听407 is primarily a laboratory course performed in the nuclear engineering thermal-hydraulics laboratory and PULSTAR reactor. Together with a lecture session, this course will provide students with laboratory practice on various fluid flow and heat transfer phenomena seen in nuclear reactor systems and design. Topics include propagation of errors, heat balance of PULSTAR reactor, heat conduction, forced heat convection, condensation, flow regime mapping, critical heat flux, friction and form losses, and natural circulation in PULSTAR reactor.
Typically offered in Fall only