Experimental results of direct containment heating by high-pressure melt ejection into the Surtsey vessel: The DCH-3 and DCH-4 tests

• Main Authors: Allen, M.D., Pilch, M., Brockmann, J.E., Tarbell, W.W. (Sandia National Labs., Albuquerque, NM (United States)), Nichols, R.T. (Ktech Corp., Albuquerque, NM (United States)), Sweet, D.W. (AEA Technology, Winfrith (United Kingdom))
• Other Authors: United States. Department of Energy.
• Format: Report
• Language: English
• Published: Sandia National Laboratories 1991
• Subjects: Heat Transfer; Bwr Type Reactors; Reactor Vessels; Reactor Components; Accidents; Oxidation; Transition Elements; Computer Calculations; Gas Analysis; Chemical Reaction Kinetics; Reactor Cooling Systems; 22 General Studies Of Nuclear Reactors; Reactor Accidents; Energy Systems; Chemical Reactions; Water Moderated Reactors 220900* > Nuclear Reactor Technology > Reactor Safety; 21 Specific Nuclear Reactors And Associated Plants; Data; Reaction Kinetics; Fluid Mechanics; Heating; Aerosols; Oxygen; Sols; Water Cooled Reactors; Kinetics; Containment; Size; Iron; Reactor Instrumentation; Particle Size; Reactors; Temperature Measurement; Test Facilities; K Codes; Mechanics; Reactor Safety; Cooling Systems; Experiment Planning; Engineered Safety Systems; Hydraulics; Pwr Type Reactors; Blowdown; Planning; Pressurization; Experimental Data; Energy Transfer; Enriched Uranium Reactors; Elements; Metals; Hydrogen; Computer Codes; Corium; 210100 > Power Reactors; Nonbreeding; Light-Water Moderated; Boiling Water Cooled; Numerical Data; Thermal Reactors; Information; Dispersions; Pressure Measurement; Power Reactors; Data Acquisition; Nonmetals; Colloids; Containment Systems; 210200 > Power Reactors; Nonboiling Water Cooled; Safety; C Codes; Containers; Surtsey
• Online Access: https://doi.org/10.2172/5081015; https://digital.library.unt.edu/ark:/67531/metadc1058322/

Two experiments, DCH-3 and DCH-4, were performed at the Surtsey test facility to investigate phenomena associated with a high-pressure melt ejection (HPME) reactor accident sequence resulting in direct containment heating (DCH). These experiments were performed using the same experimental apparatus...