Investigation of molten corium-concrete interaction phenomena and aerosol release

Conference · Thu Jan 01 00:00:00 EST 1987

OSTI ID:6439801

Spencer, B W; Thompson, D H; Armstrong, D R; Fink, J K; Gunther, W H; Kilsdonk, D J; Sehgal, B R

The Electric Power Research Institute is sponsoring a program of laboratory investigations at Argonne National Laboratory to study the interaction between molten core materials and reactor concrete basemats during postulated severe reactor accidents, with particular emphasis on measurements of the magnitude and chemical species present in the aerosol releases. The approach in this program is to sustain internal heat generation in reactor-material corium using direct electrical heating and to develop test operating and diagnostics capabilities with a series of small- and intermediate-scale scoping tests followed by fully instrumented large-scale testing. Real reactor materials (UO2, ZrO2, oxides of stainless steel, plus metallics) are used, with small amounts of La2O3, BaO, and SrO added to simulate nonvolatile fission products. In intermediate-scale scoping tests completed to date, corium inventories of up to 29 kg have been heated with power inputs in excess of 1 kW/kg melt. The measured concrete ablation rates have ranged from 0.9 to 3.9 mm/minute. Aerosol samples have been examined using a scanning electron microscope and show submicron particles, 2-6 micrometer spheres, and agglomerates that range from a few micrometers to string 13 micrometers in length.

• Research Organization: Argonne National Lab., IL (USA); Electric Power Research Inst., Palo Alto, CA (USA)
• DOE Contract Number: W-31109-ENG-38
• OSTI ID: 6439801
• Report Number(s): CONF-870816-27; ON: DE87011407
• Resource Relation: Conference: 24. national heat transfer conference and exhibition, Pittsburgh, PA, USA, 9 Aug 1987; 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
CONCRETES
FLUID-STRUCTURE INTERACTIONS
CORIUM
FISSION PRODUCT RELEASE
MELTDOWN
RADIOACTIVE AEROSOLS
REACTOR MATERIALS
ACCIDENTS
AEROSOLS
BUILDING MATERIALS
COLLOIDS
DISPERSIONS
MATERIALS
REACTOR ACCIDENTS
SOLS
220900* - Nuclear Reactor Technology- Reactor Safety
220502 - Nuclear Reactor Technology- Environmental Aspects- Radioactive Effluents