BNL program in support of LWR degraded-core accident analysis
Conference
·
OSTI ID:6807393
Two major sources of loading on dry watr reactor containments are steam generatin 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 in this paper. 8 figures.
- Research Organization:
- Brookhaven National Lab., Upton, NY (USA)
- DOE Contract Number:
- AC02-76CH00016
- OSTI ID:
- 6807393
- Report Number(s):
- BNL-NUREG-32124; CONF-821037-62; ON: DE83003962
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
BUILDING MATERIALS
CHEMICAL REACTIONS
CONCRETES
CONTAINMENT
CORIUM
ENERGY TRANSFER
HEAT TRANSFER
HYDROGEN COMPOUNDS
INTERFACES
MATERIALS
OXYGEN COMPOUNDS
REACTOR ACCIDENTS
REACTOR CORE DISRUPTION
REACTORS
STEAM
WATER
WATER COOLED REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
BUILDING MATERIALS
CHEMICAL REACTIONS
CONCRETES
CONTAINMENT
CORIUM
ENERGY TRANSFER
HEAT TRANSFER
HYDROGEN COMPOUNDS
INTERFACES
MATERIALS
OXYGEN COMPOUNDS
REACTOR ACCIDENTS
REACTOR CORE DISRUPTION
REACTORS
STEAM
WATER
WATER COOLED REACTORS