Estimates of early containment loads from core melt accidents. Draft report for comment

Technical Report · Sun Dec 01 00:00:00 EST 1985

DOI:https://doi.org/10.2172/6474274· OSTI ID:6474274

The thermal-hydraulic processes and corium debris-material interactions that can result from core melting in a severe accident have been studied to evaluate the potential effect of such phenomena on containment integrity. Pressure and temperature loads associated with representative accident sequences have been estimated for the six various LWR containment types used within the United States. Summaries distilling the analyses are presented and an interpretation of the results provided. 13 refs., 68 figs., 39 tabs.

• Research Organization: US Nuclear Regulatory Commission (NRC), Washington, DC (USA). Office of Nuclear Reactor Regulation
• OSTI ID: 6474274
• Report Number(s): NUREG-1079; ON: TI86900457
• 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 SYSTEMS
MELTDOWN
THERMAL STRESSES
HYDRAULICS
THERMODYNAMICS
PWR TYPE REACTORS
FAILURES
LOADING
MATHEMATICAL MODELS
REACTOR CORES
REACTOR SAFETY
RISK ASSESSMENT
ACCIDENTS
CONTAINMENT
ENGINEERED SAFETY SYSTEMS
FLUID MECHANICS
MATERIALS HANDLING
MECHANICS
REACTOR ACCIDENTS
REACTOR COMPONENTS
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