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AbstractAbstract
[en] In the hypothetical event of a severe accident in a Light Water Reactor, scenarios in which the reactor pressure vessel (RPV) fails and the core melt mixture (called corium) relocates into the reactor cavity, cannot be excluded. The viscosity (in fact, corium rheological behaviour) plays a major role in many phenomena such as core melt down, discharge from reactor pressure vessel, interaction with structural materials (concrete,...) and spreading in a core-catcher. For these reasons, it is important to be able to predict the rheological behaviour of corium melts of different compositions (essentially based on UO2, ZrO2, FexOy and Fe for in-vessel scenarios, plus SiO2 and CaO for ex-vessel scenarios) at temperatures above solidus temperature. In the case of corium-concrete mixtures, the increase of viscosity depends not only on the increase of particles in the melts but also on the increase of the residual liquid phase viscosity (due to the increase in silica contents). The Urban correlation is used to calculate the viscosity of the carrying liquid with silica. This model was tested and gave good agreements between measured and estimated viscosities of various basalts among which one contained 18 wt% of UO2. Then, in the solidification range, the analysis of published data showed that the viscosity cannot be described by a suspension viscosity model of non-interactive spherical particles; consequently we proposed an Arrhenius type law with a multiplying factor such as ηr = exp(2.5 Cφ) and the C factor value varies between 4 and 8. This factor is more important in the case of low shear rates and low cooling rates. The analysis of the samples structure after quenching shows a dependence of this factor on the particle morphology. Finally, for a value of 6.1 of the C factor, we obtained the best agreement with experimental data for a corium spreading test at 2100 K on a horizontal surface. (author)
Original Title
Etude du comportement rheologique de melanges issus de l'interaction corium/beton
Primary Subject
Source
24 Sep 1999; 216 p; These mecanique energetique
Record Type
Report
Literature Type
Thesis/Dissertation; Numerical Data
Report Number
Country of publication
ALUMINIUM OXIDES, BASALT, CALCIUM OXIDES, CEA CADARACHE, COMPARATIVE EVALUATIONS, CONCRETES, CORIUM, EXPERIMENTAL DATA, G CODES, IRON OXIDES, LEAD, MICROSTRUCTURE, MORPHOLOGY, PRESSURE VESSELS, PWR TYPE REACTORS, REACTOR ACCIDENTS, RHEOLOGY, RISK ASSESSMENT, SCANNING ELECTRON MICROSCOPY, SILICON OXIDES, SOLIDIFICATION, SURFACE TENSION, T CODES, THERMAL CONDUCTIVITY, TIN, TIN BASE ALLOYS, URANIUM DIOXIDE, VISCOSITY
ACCIDENTS, ACTINIDE COMPOUNDS, ALKALINE EARTH METAL COMPOUNDS, ALLOYS, ALUMINIUM COMPOUNDS, BUILDING MATERIALS, CALCIUM COMPOUNDS, CEA, CHALCOGENIDES, COMPUTER CODES, CONTAINERS, DATA, ELECTRON MICROSCOPY, ELEMENTS, ENRICHED URANIUM REACTORS, EVALUATION, FRENCH ORGANIZATIONS, IGNEOUS ROCKS, INFORMATION, IRON COMPOUNDS, MATERIALS, METALS, MICROSCOPY, NATIONAL ORGANIZATIONS, NUMERICAL DATA, OXIDES, OXYGEN COMPOUNDS, PHASE TRANSFORMATIONS, PHYSICAL PROPERTIES, POWER REACTORS, REACTORS, ROCKS, SILICON COMPOUNDS, SURFACE PROPERTIES, THERMAL REACTORS, THERMODYNAMIC PROPERTIES, TIN ALLOYS, TRANSITION ELEMENT COMPOUNDS, URANIUM COMPOUNDS, URANIUM OXIDES, VOLCANIC ROCKS, WATER COOLED REACTORS, WATER MODERATED REACTORS
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