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.
• Language: unknown
• Published: 2015
• Subjects: 22 GENERAL STUDIES OF NUCLEAR REACTORS; 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; SURRY-1 REACTOR; CONTAINMENT; SURRY-2 REACTOR; SURRY-3 REACTOR; SURRY-4 REACTOR; RADIATION HEATING; HEAT TRANSFER; HYDRAULICS; REACTOR SAFETY; SCALE MODELS; MELTDOWN; CHEMICAL REACTION KINETICS; HYDROGEN; COMBUSTION; DYNAMIC LOADS; CONTAINMENT BUILDINGS; REACTOR COMPONENTS; MELTING; CORIUM; Surtsey
• Online Access: http://www.osti.gov/servlets/purl/10165960; https://www.osti.gov/biblio/10165960; https://doi.org/10.2172/10165960

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...