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Filtering by: Committee Member Marcum, Wade R. Subject Gas cooled reactors -- Oregon -- Corvallis -- Safety measures -- Testing

Scaling analysis of the OSU high temperature test facility during a pressurized conduction cooldown event using RELAP5-3D

Creator:

Castañeda, Juan A.

Abstract:

In early 2000, the Generation IV International Forum (GIF) was created to perform research and development for the next generation nuclear systems. Among the selected nuclear systems was the Very High Temperature Gas-Cooled Reactor (VHTR). Then in 2008, the U.S. Department of Energy (DOE) decided that the Next Generation Nuclear...

Resource Type:

Masters Thesis