In the most challenging nuclear power plant accidents, transient critical heat flux (CHF) is a primary phenomenon that drives peak cladding temperature and ultimately fuel failure. It is not yet determined whether the use of steady-state CHF methods can accurately predict transient CHF under the conditions of a blowdown due...
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...
The purposes of this paper are to present the results of an experimental effort to measure the level swell in an air/water system and to generate a methodology for determining the volume-averaged void fraction within the Oregon State University (OSU) Advanced Plant Experiment (APEX) Test Facility. The results were then...