Direct heating containment vessel interactions code (DHCVIC) and prediction of SNL ''SURTSEY'' test DCH-1

• Main Authors: Ginsberg, T., Tutu, N.
• Format: Article in Journal/Newspaper
• Language: English
• Published: Brookhaven National Lab., Upton, NY (USA). Nuclear Energy Dept. 1986
• Subjects: Containment; Heating; Reactor Vessels; Reactors; Water Cooled Reactors; Reactor Core Disruption; Engineered Safety Systems; 210200 > Power Reactors; Nonbreeding; Light-Water Moderated; Nonboiling Water Cooled; Pwr Type Reactors; Blowdown; Containment Systems; 22 General Studies Of Nuclear Reactors; Reactor Accidents; Accidents; Meltdown; 21 Specific Nuclear Reactors And Associated Plants; Water Moderated Reactors 220900* > Nuclear Reactor Technology > Reactor Safety; Containers; Surtsey
• Online Access: https://digital.library.unt.edu/ark:/67531/metadc1068690/

High-pressure melt ejection from PWR vessels has been identified as a severe core accident scenario which could potentially lead to ''early'' containment failure. Melt ejection, followed by dispersal of the melt by high velocity steam in the cavity beneath the PWR vessel could, a...