BNL program in support of LWR degraded-core accident analysis

Conference · Fri Jan 01 00:00:00 EST 1982

OSTI ID:6807393

Ginsberg, T; Greene, G A

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
• Resource Relation: Conference: 10. water reactor safety research information conference, Gaithersburg, MD, USA, 12 Oct 1982; Other Information: Portions are illegible in microfiche products
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
REACTOR CORE DISRUPTION
CONTAINMENT
WATER COOLED REACTORS
CHEMICAL REACTIONS
CONCRETES
CORIUM
HEAT TRANSFER
INTERFACES
STEAM
WATER
ACCIDENTS
BUILDING MATERIALS
ENERGY TRANSFER
HYDROGEN COMPOUNDS
MATERIALS
OXYGEN COMPOUNDS
REACTOR ACCIDENTS
REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety