BNL severe-accident sequence experiments and analysis program. [PWR; BWR]

Conference · Sat Jan 01 00:00:00 EST 1983

OSTI ID:5568078

Greene, G A; Ginsberg, T; Tutu, N K

In the analysis of degraded core accidents, the two major sources of pressure loading on light water reactor containments are: steam generation from core debris-water thermal interactions; and molten core-concrete interactions. Experiments are in progress at BNL in support of analytical model development related to aspects of the above containment loading mechanisms. The work supports development and evaluation of the CORCON (Muir, 1981) and MARCH (Wooton, 1980) computer codes. Progress in the two programs is described.

• Research Organization: Brookhaven National Lab., Upton, NY (USA)
• DOE Contract Number: AC02-76CH00016
• OSTI ID: 5568078
• Report Number(s): BNL-NUREG-33664; CONF-8310143-2; ON: DE83017944
• Resource Relation: Conference: 11. NRC water reactor safety research information meeting, Gaithersburg, MD, USA, 14 Oct 1983
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
BWR TYPE REACTORS
CONTAINMENT BUILDINGS
MELTDOWN
STRESS ANALYSIS
THERMAL STRESSES
CHEMICAL REACTIONS
MOLTEN METAL-WATER REACTIONS
PRESSURE GRADIENTS
PWR TYPE REACTORS
COMPUTER CALCULATIONS
CORIUM
HEAT TRANSFER
HYDRAULICS
REACTOR SAFETY
ACCIDENTS
CONTAINMENT
ENERGY TRANSFER
FLUID MECHANICS
MECHANICS
REACTOR ACCIDENTS
REACTORS
SAFETY
STRESSES
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210100 - Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled