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. ), Nichols, R.T. ), Sweet, D.W. )
• Language: unknown
• Published: 2008
• Subjects: 22 GENERAL STUDIES OF NUCLEAR REACTORS; 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; BWR TYPE REACTORS; REACTOR VESSELS; PWR TYPE REACTORS; AEROSOLS; BLOWDOWN; C CODES; CHEMICAL REACTION KINETICS; CHEMICAL REACTIONS; COMPUTER CALCULATIONS; CONTAINMENT; CONTAINMENT SYSTEMS; CORIUM; DATA ACQUISITION; EXPERIMENT PLANNING; EXPERIMENTAL DATA; GAS ANALYSIS; HEAT TRANSFER; HEATING; HYDRAULICS; HYDROGEN; IRON; K CODES; OXIDATION; OXYGEN; PARTICLE SIZE; PRESSURE MEASUREMENT; PRESSURIZATION; REACTOR ACCIDENTS; REACTOR COOLING SYSTEMS; REACTOR INSTRUMENTATION; REACTOR SAFETY; TEMPERATURE MEASUREMENT; TEST FACILITIES; ACCIDENTS; COLLOIDS; COMPUTER CODES; CONTAINERS; COOLING SYSTEMS; DATA; DISPERSIONS; ELEMENTS; ENERGY SYSTEMS; ENERGY TRANSFER; ENGINEERED SAFETY SYSTEMS; ENRICHED URANIUM REACTORS; FLUID MECHANICS; INFORMATION; KINETICS; Surtsey
• Online Access: http://www.osti.gov/servlets/purl/5081015; https://www.osti.gov/biblio/5081015; https://doi.org/10.2172/5081015

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...