Results of EPRI/ANL DCH investigations and model development

• Main Authors: Spencer, B.W., Sienicki, J.J., Sehgal, B.R., Merilo, M.
• Language: unknown
• Published: 2008
• Subjects: 22 GENERAL STUDIES OF NUCLEAR REACTORS; 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; ZION-1 REACTOR; SCALE MODELS; ZION-2 REACTOR; BLOWDOWN; C CODES; CHEMICAL REACTIONS; CONTAINMENT; CORIUM; H CODES; HEAT TRANSFER; HEATING; HYDRAULICS; HYDROGEN; LOSS OF COOLANT; M CODES; OXIDATION; REACTOR SAFETY; S CODES; TESTING; WATER; ACCIDENTS; COMPUTER CODES; ELEMENTS; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; FLUID MECHANICS; HYDROGEN COMPOUNDS; MECHANICS; NONMETALS; OXYGEN COMPOUNDS; POWER REACTORS; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTORS; SAFETY; STRUCTURAL MODELS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS; Surtsey
• Online Access: http://www.osti.gov/servlets/purl/6519463; https://www.osti.gov/biblio/6519463

The results of a series of five experiments are described addressing the severity and mitigation of direct containment heating. The tests were performed in a 1:30 linear scale mockup of the Zion PWR containment system using a reactor-material corium melt consisting of 60% UO/sub 2/, 16% ZrO/sub 2/,...