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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

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

A. Martin, F. Lestang, S. Bellet, D. Guichard, C. Vit, S. Cornille, A. Barbier, F. Huvelin
Proc. ASME. PVP2009, Volume 7: Operations, Applications and Components, 383-391, July 26–30, 2009
Paper No: PVP2009-77390
https://doi.org/10.1115/PVP2009-77390
View Paper titled, 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
Open the PDF for 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 in another window
Topics: Computational fluid dynamics, Fracture mechanics, Pressure, Pressurized water reactors, Reactor vessels, Thermal shock
Proceedings Papers

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

A. Martin, S. Bosse, F. Lestang
Proc. ASME. PVP2007, Volume 7: Operations, Applications and Components, 45-56, July 22–26, 2007
Paper No: PVP2007-26316
https://doi.org/10.1115/PVP2007-26316
View Paper titled, 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
Open the PDF for 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 in another window
Topics: Computational fluid dynamics, Cooling, Emergencies, Pressurized water reactors, Reactor vessels, Safety, Thermal shock
Proceedings Papers

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

A. Martin, A. Dahl, F. Lestang, S. Bellet, F. Beaud, Ph. Gilles, D. Guichard, Ph. Dolleans, S. Cornille, L. Maas
Proc. ASME. PVP2008, Volume 7: Operations, Applications and Components, 597-604, July 27–31, 2008
Paper No: PVP2008-61717
https://doi.org/10.1115/PVP2008-61717
View Paper titled, 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
Open the PDF for 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 in another window
Topics: Fracture mechanics, Power stations, Reactor vessels, Safety, Thermal hydraulics, Thermal shock
Proceedings Papers

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

A. Martin, S. Bugat, A. Dahl, F. Lestang, F. Beaud
Proc. ASME. PVP2004, RPV Integrity and Fracture Mechanics, 1-9, July 25–29, 2004
Paper No: PVP2004-2719
https://doi.org/10.1115/PVP2004-2719
View Paper titled, Assessment of the Reactor Pressure Vessel Integrity in PTS Conditions: ThermalHydraulic and ThermoMechanical Studies of a Safety Injection in a Four Loop PWR Plant
Open the PDF for Assessment of the Reactor Pressure Vessel Integrity in PTS Conditions: ThermalHydraulic and ThermoMechanical Studies of a Safety Injection in a Four Loop PWR Plant in another window
Topics: Pressurized water reactors, Reactor vessels, Safety, Thermomechanics, Transients (Dynamics), Vessels, Geometry, Stress, Base metals, Cladding systems (Building)
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