Molten Corium Concrete Interaction: Post-calculations of 1D ARTEMIS Tests with the TOLBIAC-ICB Code

Conference · Sat Jul 01 04:00:00 EDT 2006

OSTI ID:21016380

Spindler, B; Veteau, J M ^[1]

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1. CEA DTN/SE2T/LPTM, 17 rue des Martyrs, 38054 Grenoble (France)

In the framework of R and D on Severe Accidents in PWRs, the TOLBIAC-ICB code was developed by CEA in the frame of an agreement with EDF to estimate the time of concrete melt-through in the case of interaction of corium with the reactor basemat. TOLBIAC-ICB simulates the 2D time evolution of the border of the reactor pit, for various compositions of concrete. The ideal phase segregation model is used: it is assumed that the temperature at the interface between the crust at the walls and the liquid of the pool is the liquidus temperature of the pool; the crust is composed of the refractory materials. Furthermore, the crust is supposed to be porous thereby allowing gas flow through it as well as a perfect and immediate mixing of the molten concrete with the pool. A main characteristic of TOLBIAC-ICB is that it is coupled with the GEMINI2 code to provide the thermodynamic data of the mixture in the pool. In the background of the validation of the code, this paper presents the simulation of tests 2 and 6 of the first tests series of the ARTEMIS experimental program, which simulates Molten Corium Concrete Interaction through tests conducted with molten salts. A summary of the experimental results is given: experimental evidence of crust, pool, interface and liquidus temperature, pool composition, and estimation of the heat transfer coefficient at the interface. Finally, the results of the post-calculations performed with TOLBIAC-ICB, including some sensitivity studies are presented and discussed. (authors)

• Research Organization: American Nuclear Society, 555 North Kensington Avenue, La Grange Park, IL 60526 (United States)
• OSTI ID: 21016380
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
CEA
CONCRETES
CORIUM
GAS FLOW
HEAT TRANSFER
INTERACTIONS
INTERFACES
LIQUIDS
MIXTURES
MOLTEN SALTS
PONDS
POROUS MATERIALS
PWR TYPE REACTORS
SENSITIVITY ANALYSIS
T CODES
VALIDATION