Short Summary:The thermal-hydraulic team has actively contributed to the Generic Safety Issue (GSI) 191 resolution project, developing computational and experimental capabilities and supporting the nuclear power industry with thermal-hydraulic analyses of different aspects of the issue.Abstract:The … [Read more...]
Archives for September 2017
Steam Condensation Test Facility
The steam-air condensation facility investigates the phenomena of direct contact condensation that occurs when steam comes in direct contact with water creating a violent and complicated exchange of mass and energy. The heat transfer coefficient between the steam and water is calculated, as well as … [Read more...]
Evaluation and Testing of HTGR Reactor Building Response to Depressurization Accidents
The analysis and understanding of air ingress events are an important aspect of the design of high-temperature gas-cooled reactor (HTGR). During accident conditions (depressurized loss of forced cooling, D-LOFC) air may enter into the reactor pressure vessel as a result of a break in the helium … [Read more...]
Critical Heat Flux Test Facility
The Critical Heat Flux / Departure from Nucleate Boiling test loop provides a means of evaluating the DNB performance of test geometries representative of commercial pressurized water reactor (PWR) nuclear fuel. The test facility has operated at the Product Engineering Development Laboratory, which … [Read more...]
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