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Communication Dans Un Congrès Année : 2015

Needs for large mass prototypic corium experiments the PLINIUS-2 platform

Résumé

Corium is the molten material formed after meltdown of a nuclear reactor core during a severe accident. In order to improve the understanding and modelling of corium behavior, experiments are needed both for LWRs and GenIV fast reactors. Experiments using low temperature simulant materials, thanks to lower costs and constraints, allow the testing of a larger number of configurations and the determination of correlations. But some crucial corium phenomena cannot be reproduced at low temperatures such as the importance of radiation heat transfer or the presence of a large (up to 1000 K) liquidus-solidus interval. Consequently, some experiments are performed with high temperature simulant materials alumina thermite as well as refractory oxides. However, it is not feasible to simulate all the aspects of corium phenomenology, especially its high temperature physico-chemistry. Therefore, even though the use of depleted uranium implies a series of protective and regulatory measures, the need for prototypic corium experimented is supported through several examples Another important aspect of experiment design deals with scaling. Small or medium scale corium experiments are easier to operate and only a few large scale (>100 kg) facilities have been built. Several effects are only visible with significant masses, as for instance, the formation of a corium cake during FCI or all the phenomena controlled by crust strength, such as underwater spreading or corium jet ablation. CEA is currently designing a new large prototypic corium platform PLINIUS-2 for both LWR and SFR corium experimental research. Its main characteristics will be presented.
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Dates et versions

cea-02509240 , version 1 (16-03-2020)

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  • HAL Id : cea-02509240 , version 1

Citer

C. Journeau, L. Buffe, J.-F. Haquet, P. Piluso, G. Willermoz. Needs for large mass prototypic corium experiments the PLINIUS-2 platform. NURETH 2015 - 16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Aug 2015, Chicago, United States. ⟨cea-02509240⟩

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