Výsledky vyhledávání - "Lepareux, Michel"

Akademický článek

Hydrodynamic loads on a PWR primary circuit due to a LOCA

Autor: Robbe, Marie-France ^*, Lepareux, Michel, Trollat, Christophe

Publikováno v: In Nuclear Engineering and Design 2002 211(2):189-228

Interpretation with the Europlexus code of the MARA8 experiment simulating a hypothetical Core Disruptive Accident

Autor: Robbe, Marie-France, Lepareux, Michel, Cariou, Yves

Publikováno v: 2nd Student Conference of the American Nuclear Society
2nd Student Conference of the American Nuclear Society, American Nuclear Society, Apr 2002, Penn State University, United States

International audience; In the case of a Hypothetical Core Disruptive Accident (HCDA) in a Liquid Metal Fast Breeder Reactor, the interaction between the fuel and the liquid sodium leads to the formation of a bubble of gas at high pressure in the cor

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=dedup_wf_001::aacd66de960382d0ed7a8ddb73704298
https://cea.hal.science/cea-03081905/document

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Documentation théorique : Modélisation des tuyauteries dans EUROPLEXUS

Autor: GALON, Pascal, Lepareux, Michel

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::64c6c26cde5afc8055d79f94dff3b543

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Description of the MARS small scale replica of a Fast Breeder Reactor and of the numerical models used to simulate a Hypothetical Core Disruptive Accident in the test-facility

Autor: Robbe, Marie-France, Cariou, Yves, Lepareux, Michel, Treille, Eloi

Publikováno v: International colloquium in mechanics of solids, fluids, structures and interactions
International colloquium in mechanics of solids, fluids, structures and interactions, Aug 2000, Nha Trang, Vietnam. pp.725-734

In case of a Hypothetical Core Disruptive Accident (HCDA) in a Liquid Metal Reactor, the interaction between fuel and liquid sodium creates a high pressure gas bubble in the core. The violent expansion of this bubble loads the vessel and the internal

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=od______3515::53cefc3e2740dee646858fbc5fbb43b5
https://cea.hal.science/cea-04071532

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Scoping calculations of an in-vessel steam explosion. Castem-Plexus computations

Autor: Robbe, Marie-France, Lepareux, Michel

Publikováno v: ICONE 8: Proceedings of the Eighth International Conference on Nuclear Engineering
ICONE8-8th International Conference on Nuclear Engineering
ICONE8-8th International Conference on Nuclear Engineering, ASME, Apr 2000, Baltimore, United States. pp.ICONE-8203

International audience; Steam explosion is considered as a potential risk for PWR nuclear power plants in case of a severe accident. The loss of coolant can cause the degradation of the core and its melting. By falling down in the water remaining in

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=od______3515::3f10eb5559bf0c3f4c5d7235a8f611cd
https://cea.hal.science/cea-04044400

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Hydrodynamic Loads on a PWR Primary Circuit due to a LOCA - Pipe Computations with the CASTEM-PLEXUS Code

Autor: Robbe, Marie-France, Lepareux, Michel, Trollat, Christophe

Publikováno v: SMIRT 15-15th International Conference on Structural Mechanics In Reactor Technology
SMIRT 15-15th International Conference on Structural Mechanics In Reactor Technology, Aug 1999, Seoul, South Korea. pp.J05/4, 199-206

International audience; The hydrodynamic loads due to a LOCA are computed with the CASTEM-PLEXUS code for a PWR primary circuit. An hydraulic model of the complete circuit (pipes, pumps, steam generators and reactor) is performed here assuming rigid

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=dedup_wf_001::7bf66160f9eb62d3961e0d33df8fd700
https://hal-cea.archives-ouvertes.fr/cea-03122148

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Screening calculations on the vessel lower head behaviour due to an in-vessel steam explosion

Autor: Robbe, Marie-France, Lepareux, Michel, Vivien, Nicolas, CENERINO, Gerard

Publikováno v: SMIRT 14-14th International Conference on Structural Mechanics In Reactor Technology
SMIRT 14-14th International Conference on Structural Mechanics In Reactor Technology, Aug 1997, Lyon, France. pp.451-458

International audience; The mechanical consequences of a steam explosion on a PWR lower plenum vessel are estimated through a parametric study regarding the corium location, the kinetics to transfer the corium energy to the water and the water consti

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=dedup_wf_001::4aea2adab1f34e04df55b1804b81e707
https://cea.hal.science/cea-03120015/file/fondcuve_SMIRT.pdf

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