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Proceedings Papers

CFD Tools for Assessment of the Reactor Pressure Vessel Integrity in Pressure Thermal Shock Conditions: Thermalhydraulic Benchmark on the Validation Test Case UPTF

A. Martin, F. Huvelin, G. Balard, S. Bellet, B. Durand, P. Martinez
Proc. ASME. PVP2010, ASME 2010 Pressure Vessels and Piping Conference: Volume 7, 211-220, July 18–22, 2010
Publisher: American Society of Mechanical Engineers
Paper No: PVP2010-25646
https://doi.org/10.1115/PVP2010-25646
View Paper titled, CFD Tools for Assessment of the Reactor Pressure Vessel Integrity in Pressure Thermal Shock Conditions: Thermalhydraulic Benchmark on the Validation Test Case UPTF
Open the PDF for CFD Tools for Assessment of the Reactor Pressure Vessel Integrity in Pressure Thermal Shock Conditions: Thermalhydraulic Benchmark on the Validation Test Case UPTF in another window
Topics: Computational fluid dynamics, Pressure, Reactor vessels, Thermal shock
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
Publisher: American Society of Mechanical Engineers
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

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
Publisher: American Society of Mechanical Engineers
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

CFD-Tool for Thermal-Hydraulics Pressurised Thermal Shock Analysis: Qualification of the Code_Saturne

A. Martin, S. Bellet
Proc. ASME. PVP2002, Emerging Technologies in Fluids, Structures and Fluid Structure Interactions: Volume 1, Fluid Dynamics, Fluid Structure Interaction, and High Explosive Detonation, 59-64, August 5–9, 2002
Publisher: American Society of Mechanical Engineers
Paper No: PVP2002-1461
https://doi.org/10.1115/PVP2002-1461
View Paper titled, CFD-Tool for Thermal-Hydraulics Pressurised Thermal Shock Analysis: Qualification of the Code_Saturne
Open the PDF for CFD-Tool for Thermal-Hydraulics Pressurised Thermal Shock Analysis: Qualification of the Code_Saturne in another window
Topics: Computational fluid dynamics, Thermal hydraulics, Thermal shock, Temperature, Water, Fluids, Reactor vessels, Safety, Transients (Dynamics)
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
Publisher: American Society of Mechanical Engineers
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
Journal Articles

CFD-Tools Qualification for Thermal-Hydraulics Pressurized Thermal Shock Analysis

A. Martin, S. Bellet
Journal: Journal of Pressure Vessel Technology
Publisher: ASME
Article Type: Technical Papers
J. Pressure Vessel Technol. November 2003, 125(4): 418–424.
https://doi.org/10.1115/1.1616583
Published Online: November 4, 2003
View Article titled, CFD-Tools Qualification for Thermal-Hydraulics Pressurized Thermal Shock Analysis
Open the PDF for CFD-Tools Qualification for Thermal-Hydraulics Pressurized Thermal Shock Analysis in another window
Topics: Computational fluid dynamics, Fluids, Probes, Temperature, Thermal hydraulics, Thermal shock, Transients (Dynamics), Flow (Dynamics), Geometry, Boundary-value problems