Experiments to investigate direct containment heating phenomena with scaled models of the Surry Nuclear Power Plant

• Main Authors: Blanchat, T. K., Allen, M. D., Pilch, M. M., Nichols, R. T.
• Other Authors: U.S. Nuclear Regulatory Commission
• Format: Report
• Language: English
• Published: U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Systems Research. 1994
• Subjects: Heat Transfer; 210200; Hydraulics; Dynamic Loads; Chemical Reaction Kinetics; Reactor Components; 22 General Studies Of Nuclear Reactors; Power Reactors; Nonbreeding; Light-Water Moderated; Nonboiling Water Cooled; 21 Specific Nuclear Reactors And Associated Plants; Surry-2 Reactor; Surry-1 Reactor; Melting; Radiation Heating; Containment; Reactor Safety; Containment Buildings; Surry-4 Reactor; Corium 220900; Meltdown; Hydrogen; Combustion; Scale Models; Surry-3 Reactor; Surtsey
• Online Access: https://doi.org/10.2172/10165960; https://digital.library.unt.edu/ark:/67531/metadc1338797/

The Containment Technology Test Facility (CTTF) and the Surtsey Test Facility at Sandia National Laboratories are used to perform scaled experiments that simulate High Pressure Melt Ejection accidents in a nuclear power plant (NPP). These experiments are designed to investigate the effects of direct...