Experimental evaluation of the water ingression mechanism for corium cooling
Creators
- 1. Argonne National Laboratory, 9700 S. Cass Avenue, Argonne, IL 60439 (United States)
Description
Experiments were performed to assess the significance of water ingression cooling in the quenching of molten corium. Water ingression is a mechanism by which water penetrates into cracks and pores of solidified corium to enhance cooling that would otherwise be severely limited by the low thermal conductivity of the material. Quench tests were conducted with 2100 deg. C melts weighing ∼75 kg composed of UO2, ZrO2 and chemical constituents of concrete. The amount of concrete in the melts was varied between 4% and 23%. The melts were quenched with an overlying water layer; three tests were conducted at a system pressure of 1 bar and four tests at 4 bar. The measured cooling rates were found to decrease with increasing concrete content and, contrary to expectations, are essentially independent of system pressure. For the lower concrete content melts, cooling rates exceeded the conduction-limited rate with the difference being attributed to the water ingression mechanism. Measurements of the permeability of the corium 'ingots' produced by the quench tests were used to obtain a second, independent set of dryout heat flux data, which exhibits the same trend as the quench test data. The data was used to validate an existing dryout heat flux model based on corium permeability associated with thermally induced cracking. The model uses the thermal and mechanical properties of the corium and coolant, and it reproduces the very particular data trend found for the dryout heat flux as a function of concrete content. The model predicts that water ingression cooling would be most effective for concrete-free corium mixtures such as in-vessel type melts. For such a melt the model predicts a dryout heat flux of ∼400 kW/m2 at a pressure of 1 bar. The results of this study provide an experimental basis for a water ingression model that can be incorporated into computer codes used to assess accident management strategies
Additional details
Identifiers
- DOI
- 10.1016/j.nucengdes.2006.12.009;
- PII
- S0029-5493(07)00022-2;
Publishing Information
- Journal Title
- Nuclear Engineering and Design
- Journal Volume
- 237
- Journal Issue
- 9
- Journal Page Range
- p. 905-917
- ISSN
- 0029-5493
- CODEN
- NEDEAU
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 38090196
- Subject category
- S42: ENGINEERING;
- Descriptors DEI
- ACCIDENTS; CONCRETES; CONTAINERS; COOLANTS; COOLING; CORIUM; CRACKS; DRYOUT; EVALUATION; HEAT FLUX; MECHANICAL PROPERTIES; PERMEABILITY; QUENCHING; THERMAL CONDUCTIVITY; URANIUM DIOXIDE; WATER; ZIRCONIUM OXIDES
- Descriptors DEC
- ACTINIDE COMPOUNDS; BUILDING MATERIALS; CHALCOGENIDES; HYDROGEN COMPOUNDS; MATERIALS; OXIDES; OXYGEN COMPOUNDS; PHYSICAL PROPERTIES; THERMODYNAMIC PROPERTIES; TRANSITION ELEMENT COMPOUNDS; URANIUM COMPOUNDS; URANIUM OXIDES; ZIRCONIUM COMPOUNDS
Optional Information
- Copyright
- Copyright (c) 2007 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.