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G. Bezdikian
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Journal Articles

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

A. Martin, S. Benhamadouche, G. Bezdikian, F. Beaud, F. Lestang
Journal: Journal of Pressure Vessel Technology
Article Type: Research Papers
J. Pressure Vessel Technol. June 2011, 133(3): 031302.
https://doi.org/10.1115/1.3027494
Published Online: April 7, 2011
View Article titled, 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
Open the PDF for 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 in another window
Topics: Boundary-value problems, Computational fluid dynamics, Fluids, Geometry, Nozzles, Safety, Temperature, Thermal shock, Transients (Dynamics), Turbulence
Proceedings Papers

Assessment of the French Reactor Pressure Vessel Integrity in PTS Conditions. Thermalhydraulic and Thermomechanical Studies of the Small Break LOCA in a Three Loop PWR Plant

A. Martin, S. Bugat, F. Ternon Morin, S. Bellet, G. Bezdikian
Proc. ASME. PVP2002, Fatigue, Fracture and Damage Analysis, Volume 2, 79-89, August 5–9, 2002
Paper No: PVP2002-1353
https://doi.org/10.1115/PVP2002-1353
View Paper titled, Assessment of the French Reactor Pressure Vessel Integrity in PTS Conditions. Thermalhydraulic and Thermomechanical Studies of the Small Break LOCA in a Three Loop PWR Plant
Open the PDF for Assessment of the French Reactor Pressure Vessel Integrity in PTS Conditions. Thermalhydraulic and Thermomechanical Studies of the Small Break LOCA in a Three Loop PWR Plant in another window
Topics: Pressurized water reactors, Reactor vessels, Thermomechanics, Transients (Dynamics), Vessels, Stress, Base metals, Cladding systems (Building), Finite element analysis, Geometry
Proceedings Papers

French RPV Assessment — Contribution of Expertises in Mechanical Analyses

G. Bezdikian, Y. Rouillon, J. Bourgoin
Proc. ASME. PVP2002, Fatigue, Fracture and Damage Analysis, Volume 2, 59-71, August 5–9, 2002
Paper No: PVP2002-1351
https://doi.org/10.1115/PVP2002-1351
View Paper titled, French RPV Assessment — Contribution of Expertises in Mechanical Analyses
Open the PDF for French RPV Assessment — Contribution of Expertises in Mechanical Analyses in another window
Topics: Brittle fracture, Cladding systems (Building), Computation, Design, Ductility, Failure, Finite element analysis, Fluence (Radiation measurement), Fuel management, Inspection
Proceedings Papers

PWR Nuclear Power Plants Reactor Vessel and Coolant System Cast Duplex Stainless Steel Elbows: New Results in Integrity Analysis

G. Bezdikian, C. Faidy, P. Cambefort, D. Moinereau
Proc. ASME. PVP2003, Design and Analysis of Pressure Vessels and Piping: Implementation of ASME B31, Fatigue, ASME Section VIII, and Buckling Analyses, 91-103, July 20–24, 2003
Paper No: PVP2003-2188
https://doi.org/10.1115/PVP2003-2188
View Paper titled, PWR Nuclear Power Plants Reactor Vessel and Coolant System Cast Duplex Stainless Steel Elbows: New Results in Integrity Analysis
Open the PDF for PWR Nuclear Power Plants Reactor Vessel and Coolant System Cast Duplex Stainless Steel Elbows: New Results in Integrity Analysis in another window
Topics: Coolants, Nuclear power stations, Pressurized water reactors, Reactor vessels, Stainless steel, Computation, Finite element analysis, Nuclear reactor coolants, Databases, Ductility
Proceedings Papers

French R&D Program for RPV Aging Management

H. Churier-Bossennec, D. Moinereau, P. Todeschini, C. Faidy, G. Bezdikian
Proc. ASME. PVP2004, Aging Management and License Renewal, 127-132, July 25–29, 2004
Paper No: PVP2004-2976
https://doi.org/10.1115/PVP2004-2976
View Paper titled, French R&D Program for RPV Aging Management
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Topics: Design, Feedback, Fluence (Radiation measurement), Fracture toughness, Industrial research, Risk, Rupture, Safety, Surveillance, Transients (Dynamics)
Proceedings Papers

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

A. Martin, D. Monfort, G. Bezdikian, F. Beaud, F. Lestang, C. Vit
Proc. ASME. PVP2005, Volume 7: Operations, Applications, and Components, 33-40, July 17–21, 2005
Paper No: PVP2005-71585
https://doi.org/10.1115/PVP2005-71585
View Paper titled, 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
Open the PDF for 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 in another window
Topics: Computational fluid dynamics, Fluids, Pressure, Reactor vessels, Safety, Temperature, Thermal shock, Transients (Dynamics), Vessels, Accidents
Proceedings Papers

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

A. Martin, S. Benhamadouche, G. Bezdikian, F. Beaud, F. Lestang
Proc. ASME. PVP2006-ICPVT-11, Volume 7: Operations, Applications, and Components, 67-74, July 23–27, 2006
Paper No: PVP2006-ICPVT-11-93311
https://doi.org/10.1115/PVP2006-ICPVT-11-93311
View Paper titled, 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
Open the PDF for 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 in another window
Topics: Computational fluid dynamics, Pressure, Reactor vessels, Thermal shock, Transients (Dynamics), Turbulence, Vessels, Accidents, Coolants, Cooling