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Proceedings Papers

Overview of the Doel 3 and Tihange 2 Reactor Pressure Vessel Safety Cases

Michel De Smet, Jean Van Vyve
Proc. ASME. PVP2016, Volume 1A: Codes and Standards, V01AT01A062, July 17–21, 2016
Paper No: PVP2016-63878
https://doi.org/10.1115/PVP2016-63878
View Paper titled, Overview of the Doel 3 and Tihange 2 Reactor Pressure Vessel Safety Cases
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Topics: Reactor vessels, Safety, Hydrogen, Irradiation (Radiation exposure), Accidents, Ductility, Embrittlement, Inspection, Mechanical testing, Shells
Proceedings Papers

Root Cause Analysis and Characterisation of the Doel 3 and Tihange 2 Reactor Pressure Vessel Flaws

Séverine De Vroey, Evy De Bruycker, Michel De Smet, Jacqueline Stubbe
Proc. ASME. PVP2016, Volume 1A: Codes and Standards, V01AT01A065, July 17–21, 2016
Paper No: PVP2016-63883
https://doi.org/10.1115/PVP2016-63883
View Paper titled, Root Cause Analysis and Characterisation of the Doel 3 and Tihange 2 Reactor Pressure Vessel Flaws
Open the PDF for Root Cause Analysis and Characterisation of the Doel 3 and Tihange 2 Reactor Pressure Vessel Flaws in another window
Topics: Reactor vessels, Root cause analysis, Hydrogen, Pressurized water reactors, In-service inspection, Low cycle fatigue, Manufacturing, Pressure vessels, Safety, Stress
Proceedings Papers

Material Properties of Reactor Pressure Vessel Shells Affected by Hydrogen Flaking

Robert Gérard, Michel De Smet, Rachid Chaouadi
Proc. ASME. PVP2016, Volume 1A: Codes and Standards, V01AT01A066, July 17–21, 2016
Paper No: PVP2016-63901
https://doi.org/10.1115/PVP2016-63901
View Paper titled, Material Properties of Reactor Pressure Vessel Shells Affected by Hydrogen Flaking
Open the PDF for Material Properties of Reactor Pressure Vessel Shells Affected by Hydrogen Flaking in another window
Topics: Hydrogen, Materials properties, Reactor vessels, Shells, Safety, Irradiation (Radiation exposure), Fracture toughness, Accidents, Cycles, Embrittlement
Proceedings Papers

Stress and Fatigue Analysis Considering Thermal Stratification With the THERMAXS Code

Adama Diaby, Michel De Smet
Proc. ASME. PVP2009, Volume 3: Design and Analysis, 849-853, July 26–30, 2009
Paper No: PVP2009-77912
https://doi.org/10.1115/PVP2009-77912
View Paper titled, Stress and Fatigue Analysis Considering Thermal Stratification With the THERMAXS Code
Open the PDF for Stress and Fatigue Analysis Considering Thermal Stratification With the THERMAXS Code in another window
Topics: Fatigue analysis, Stress, Thermal stratification, Feedwater, Boilers, Nozzles, Transients (Dynamics), Design, Nuclear power stations, Computers