Spreading of molten corium in Mk I geometry following vessel meltthrough

Conference · Fri Jan 01 00:00:00 EST 1988

OSTI ID:6572846

Sienicki, J J; Farmer, M T; Spencer, B W

A one-dimensional, multicell, Eulerian computer code is under development to predict the gravity-driven spreading dynamics and thermal interactions of a molten corium layer flowing horizontally over a concrete substrate. The code is compared to recent experiments in which molten mixtures of iron and aluminum oxide flowed over concrete in the presence and absence of water. Results are presented from scoping calculations for the Mk I BWR system investigating the spreading-induced penetration immediately following the drainage of a predominantly oxide molten corium mixture from a localized breach in the reactor vessel. 12 refs., 7 figs.

• Research Organization: Argonne National Lab., IL (USA)
• DOE Contract Number: W-31109-ENG-38
• OSTI ID: 6572846
• Report Number(s): CONF-881011-34; ON: DE89003973
• Resource Relation: Conference: Joint meeting of the European Nuclear Society and the American Nuclear Society, Washington, DC, USA, 30 Oct 1988; Other Information: Portions of this document are illegible in microfiche products
• 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
CORIUM
M CODES
ALUMINIUM OXIDES
CONCRETES
CONTAINMENT
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
IRON
MATHEMATICAL MODELS
MELTDOWN
REACTOR SAFETY
WATER
ACCIDENTS
ALUMINIUM COMPOUNDS
BUILDING MATERIALS
CHALCOGENIDES
COMPUTER CODES
ELEMENTS
ENERGY TRANSFER
HYDROGEN COMPOUNDS
MATERIALS
MECHANICS
METALS
OXIDES
OXYGEN COMPOUNDS
REACTOR ACCIDENTS
REACTORS
SAFETY
TRANSITION ELEMENTS
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
220502 - Nuclear Reactor Technology- Environmental Aspects- Radioactive Effluents
210100 - Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled