TURC1: large scale metallic melt-concrete interaction experiments and analysis
Technical Report
·
OSTI ID:5982796
Two large scale molten debris-concrete experiments, TURC1T, a thermite-concrete interaction experiment, and TURC1SS, a stainless steel-concrete experiment, are reported here. The experiments consisted of teeming molten debris (>100 kg) onto limestone/common sand concrete. The molten debris was allowed to cool naturally. The concrete ablation rate, composition of evolved gases, and aerosol data are presented. The experimental results have been compared to CORCON calculations in order to validate the code. This comparison showed that, while some parts of the code performed well (chemical equilibrium model), other sections required further model development (melt-concrete heat transfer model). An analysis of the two experiments was performed using a new analysis model. The results of the analysis seem to suggest that the heat transfer mechanism of concrete ablation is similar to nucleate boiling heat transfer, rather than gas film heat transfer. 32 refs., 82 figs., 23 tabs.
- Research Organization:
- Sandia National Labs., Albuquerque, NM (USA)
- DOE Contract Number:
- AC04-76DP00789
- OSTI ID:
- 5982796
- Report Number(s):
- NUREG/CR-4420; SAND-85-0707; ON: TI86007440
- Country of Publication:
- United States
- Language:
- English
Similar Records
Interaction of hot solid core debris with concrete
TURC2 and 3: large scale UO/sub 2//ZrO/sub 2//Zr melt-concrete interaction experiments and analysis
Validation of core debris/concrete interactions and source term models
Technical Report
·
Sun Jun 01 00:00:00 EDT 1986
·
OSTI ID:5203250
TURC2 and 3: large scale UO/sub 2//ZrO/sub 2//Zr melt-concrete interaction experiments and analysis
Technical Report
·
Sun Jun 01 00:00:00 EDT 1986
·
OSTI ID:5436648
Validation of core debris/concrete interactions and source term models
Conference
·
Sat Dec 31 23:00:00 EST 1988
·
OSTI ID:6232931
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210100 -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ABLATION
ACCIDENTS
ALLOYS
BUILDING MATERIALS
BWR TYPE REACTORS
CHROMIUM ALLOYS
COMPUTERIZED SIMULATION
CONCRETES
CORIUM
CORROSION RESISTANT ALLOYS
ENERGY TRANSFER
FLUID FLOW
FUEL-CLADDING INTERACTIONS
HEAT TRANSFER
IRON ALLOYS
IRON BASE ALLOYS
MATERIALS
MATHEMATICAL MODELS
MELTDOWN
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR SAFETY EXPERIMENTS
REACTORS
SIMULATION
STAINLESS STEELS
STEELS
WATER COOLED REACTORS
WATER MODERATED REACTORS
210100 -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ABLATION
ACCIDENTS
ALLOYS
BUILDING MATERIALS
BWR TYPE REACTORS
CHROMIUM ALLOYS
COMPUTERIZED SIMULATION
CONCRETES
CORIUM
CORROSION RESISTANT ALLOYS
ENERGY TRANSFER
FLUID FLOW
FUEL-CLADDING INTERACTIONS
HEAT TRANSFER
IRON ALLOYS
IRON BASE ALLOYS
MATERIALS
MATHEMATICAL MODELS
MELTDOWN
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR SAFETY EXPERIMENTS
REACTORS
SIMULATION
STAINLESS STEELS
STEELS
WATER COOLED REACTORS
WATER MODERATED REACTORS