Index Catalog // ScholarsArchive@OSU

Start Over

Filtering by: Subject Water cooled reactors -- Oregon -- Corvallis Committee Member Palmer, Todd S.

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

Full Text:

), Supercritical-Water-Cooled Reactor (SCWR) and the Very-High-Temperature Reactor (VHTR). [2] In the United