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CFD-Tools for Assessment of the Reactor Pressure Vessel Integrity in Pressure Thermal Shock Conditions: Thermal-Hydraulic Methods and Main Industrial Results on the French 900 MWe PWR RPV

Autor: S. Bellet, A. Barbier, S. Cornille, D. Guichard, F. Huvelin, A. Martin, C. Vit, F. Lestang

Publikováno v: Volume 7: Operations, Applications and Components.

For the Reactor Pressure Vessel (RPV) assessment and lifetime evaluation of the nuclear plants, French Utilities apply a series of calculations including thermal-hydraulic, thermo mechanical and fracture mechanics studies in order to study the Pressu

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::2e37b6c5ffd67db149e6597e58dddf24
https://doi.org/10.1115/pvp2009-77390

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Engineering Approach for the Reactor Pressure Vessel Integrity in PTS Conditions: Thermal Hydraulic and Fracture Mechanics Studies of a Safety Injection in a Three Loop Power Plant — French Benchmark With EDF and AREVA-NP Tools

Autor: S. Cornille, A. Martin, S. Bellet, A. Dahl, Ph. Dolleans, L. Maas, F. Beaud, F. Lestang, D. Guichard, P. Gilles

Publikováno v: Volume 7: Operations, Applications and Components.

For the Reactor Pressure Vessel (RPV) assessment and Lifetime evaluation of the nuclear plants, French Utility applies a series of calculations including thermal-hydraulic, thermo mechanical and fracture mechanics studies in order to study the Pressu

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::63e334db40e52b9d3583f5bdfec2d321
https://doi.org/10.1115/pvp2008-61717

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Use of a CFD-Tool for Assessment of the Reactor Pressure Vessel Integrity in Pressurised Thermal Shock Conditions: Thermal-Hydraulic Studies of a Safety Injection in a PWR Plant — Methodology and Present Limitation

Autor: A. Martin, S. Bosse, F. Lestang

Publikováno v: Volume 7: Operations, Applications and Components.

Integrity evaluation methods for nuclear Reactor Pressure Vessels (RPVs) under Pressurised Thermal Shock (PTS) loading are applied by French Utility. They are based on the analysis of the behaviour of cracks under PTS loading conditions due to the em

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::18a19470d381a732e6d866ee065c5467
https://doi.org/10.1115/pvp2007-26316

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CFD-Tool for Assessment of the Reactor Pressure Vessel Integrity in Pressure Thermal Shock Conditions: Influence of Turbulence Model and Mesh Refinement on the Vessel Thermal Loading During PTS Transient

Autor: S. Benhamadouche, G. Bezdikian, F. Beaud, F. Lestang, A. Martin

Publikováno v: Volume 7: Operations, Applications, and Components.

Integrity evaluation methods for nuclear Reactor Pressure Vessels (RPVs) under Pressurised Thermal Shock (PTS) loading are applied by French Utility. They are based on the analysis of the behavior of relatively shallow cracks under loading PTS condit

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_dedup___::a5f11dcd67e7ba44570f6358639b0b93
https://doi.org/10.1115/pvp2006-icpvt-11-93311

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CFD-Tool for Assessment of the Reactor Pressure Vessel Integrity in Pressure Thermal Shock Conditions: Influence of Temperature Safety Injection and Fluid-Structure Thermal Coupling

Autor: G. Bezdikian, C. Vit, D. Monfort, F. Lestang, F. Beaud, A. Martin

Publikováno v: Volume 7: Operations, Applications, and Components.

Integrity evaluation methods for nuclear Reactor Pressure Vessels (RPVs) under Pressurised Thermal Shock (PTS) loading are applied by French Utility. They are based on the analysis of the behavior of relatively shallow cracks under loading PTS condit

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::b349ddec4dc01e93a3ef845fb6bfb6fc
https://doi.org/10.1115/pvp2005-71585

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Assessment of the Reactor Pressure Vessel Integrity in PTS Conditions: ThermalHydraulic and ThermoMechanical Studies of a Safety Injection in a Four Loop PWR Plant

Autor: F. Beaud, F. Lestang, A. Martin, S. Bugat, A. Dahl

Publikováno v: RPV Integrity and Fracture Mechanics.

This paper explains the Research and Development program started at E.D.F about the cooling phenomena of a PWR vessel after a Pressurized Thermal Shock. The numerical results are obtained with the thermalhydraulic code Code_Saturne coupled with the t

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::9202447fe9aea015748414e00231cc0e
https://doi.org/10.1115/pvp2004-2719

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MANSEK and SUNHCA. Two interactive programs for the hydrophobic cluster analysis of protein sequences

Autor: Jean-Paul Mornon, G. Pantel, F. Lestang, Anne Morgat, S. Lavaitte, C. Gaboriaud, L. Lemesle-Varloot, Bernard Henrissat

Publikováno v: Bioinformatics
Bioinformatics, Oxford University Press (OUP), 1993, pp.37-44
Bioinformatics, 1993, pp.37-44

Hydrophobic cluster analysis (HCA) is an efficient method for analysing and comparing the amino acid sequences of proteins. It relies on two-dimensional representations of the sequences presently generated by simple plot programs working on microcomp

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_dedup___::15d7b8a01a3fa2c6523d46a13d1b8020
https://hal.archives-ouvertes.fr/hal-00310623

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Akademický článek

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Akademický článek

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