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Filtering by: Degree Name Master of Science (M.S.) Subject Nuclear reactor accidents

Blowdown transient critical heat flux

Creator:

Moussaoui, Musa A.

Abstract:

Occurring in the most challenging nuclear power plant accidents, transient critical heat flux (CHF) is the primary phenomenon that drives peak cladding temperature and ultimately fuel failure. It is unclear whether the use of steady-state CHF correlations can accurately predict the gross thermal-hydraulic perturbations of a blowdown in a large...

Resource Type:

Masters Thesis
Pressurized water reactor (PWR) accident analysis using the EMERALD code

Creator:

Youssefnia, Mohammed Hossein

Abstract:

A detail study of a Loss of Coolant Accident (LOCA) in a Pressurized Water Reactor was conducted in order to estimate the consequences of the accident using the computer simulation code EMERALD. An effort was undertaken to modify the EMERALD code and to make it operable on the OSU CYBER...

Resource Type:

Masters Thesis