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Hydrodynamic Loads on a PWR Primary Circuit due to a LOCA - Pipe Computations with the CASTEM-PLEXUS CodeSMIRT 15 - 15th International Conference on Structural Mechanics In Reactor Technology, Aug 1999, Seoul, South Korea. pp.J05/4, 199-206
Conference papers
cea-03122148v1
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Qualification of the numerical simulation of a Hypothetical Core Disruptive Accident on the MARA 10 test-facilityNha Trang 2000 International Colloquium, Aug 2000, Nha Trang, Vietnam. pp 746-755
Conference papers
cea-04177269v1
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Validation of the Core Disruptive Accident constitutive law of the Castem-Plexus code on the Mara8 testNha Trang'2000 International Colloquium, Aug 2000, Nha Trang, Vietnam. pp 735-744
Conference papers
cea-04177275v1
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Numerical interpretation of the MARA 10 test simulating a Hypothetical Core Disruptive Accident in a mock-up schematizing a reactorInternational Conference on Numerical Methods in Continuum Mechanics 2000, Sep 2000, Liptovsky Jan, Slovakia
Conference papers
cea-04177361v1
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Scoping calculations of an in-vessel steam explosion. Castem-Plexus computationsICONE8- 8th International Conference on Nuclear Engineering, ASME, Apr 2000, Baltimore, United States. pp.ICONE-8203
Conference papers
cea-04044400v1
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Numerical simulation of a Hypothetical Core Disruptive Accident in the MARA8 mock-up with the CASTEM-PLEXUS computer codeInternational Conference on Numerical Methods in Continuum Mechanics 2000, Sep 2000, Liptovsky Jan, Slovakia
Conference papers
cea-04177465v1
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Screening calculations on the vessel lower head behaviour due to an in-vessel steam explosionSMIRT 14 - 14th International Conference on Structural Mechanics In Reactor Technology, Aug 1997, Lyon, France. pp.451-458
Conference papers
cea-03120015v1
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Comparison of a Core Disruptive Accident simulation with the MARS experimental testInternational Conference on Numerical Methods in Continuum Mechanics 2000, Sep 2000, Liptovsky Jan, Slovakia
Conference papers
cea-04177342v1
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Assessment of the hydrodynamic loads due to a LOCA in a 3-loop PWR. Castem-Plexus computationsICONE8 - 8th International Conference on Nuclear Engineering, ASME, Apr 2000, Baltimore, United States. pp.ICONE-8199
Conference papers
cea-04044567v1
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Interpretation with the Europlexus code of the MARA8 experiment simulating a hypothetical Core Disruptive Accident2nd Student Conference of the American Nuclear Society, American Nuclear Society, Apr 2002, Penn State University, United States
Conference papers
cea-03081905v1
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Computation of the MARS test simulating a Hypothetical Core Disruptive Accident in a small scale replica of a Fast Breeder ReactorInternational Conference on Numerical Methods in Continuum Mechanics 2000, Sep 2000, Liptovsky Jan, Slovakia
Conference papers
cea-04177351v1
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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-facilityInternational colloquium in mechanics of solids, fluids, structures and interactions, Aug 2000, Nha Trang, Vietnam. pp.725-734
Conference papers
cea-04071532v1
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