We describe the model developed for integrity assessment of a reactor pressure vessel (RPV) subjected to pressurized thermal shock (PTS). The assessment is based on a multi-step simulation scheme, which includes the thermo-hydraulic, thermo-mechanical and fracture mechanics analyses. The thermo-mechanical model uses the three-dimensional finite element method (FEM) to calculate the stress fields of the reactor pressure vessel (RPV) subjected to the thermal load and pressure during large break loss of coolant accident (LBLOCA). In this contribution, the multistep simulation scheme is extended to the analysis of two-phase steam-water flow occurring in the LBLOCA situation and the fracture analysis of postulated cracks under this accident even...
International audienceIn PWR severe accident scenarios, involving a relocation of corium (core melt)...
Pressurized thermal shock experiments are performed in the Prometey Institute for the purpose of inv...
International audienceIn PWR severe accident scenarios, involving a relocation of corium (core melt)...
We describe the model developed for integrity assessment of a reactor pressure vessel (RPV) subjecte...
The present work deals with the development of a detailed Finite Element (FE) model of the Atucha II...
In the structural integrity assessment of a pressurized water reactor pressure vessel (RPV) during p...
Comparative analyses have been performed with 3-D finite element (FE) models for a six loop cladded ...
The Reactor Pressure Vessel (RPV) has long been considered one of the most reliable components in Pr...
The considered research activity deals with the application of a chain of numerical codes, in order ...
International audienceIn PWR severe accident scenarios, involving a relocation of corium (core melt)...
International audienceIn PWR severe accident scenarios, involving a relocation of corium (core melt)...
International audienceIn PWR severe accident scenarios, involving a relocation of corium (core melt)...
International audienceIn PWR severe accident scenarios, involving a relocation of corium (core melt)...
International audienceIn PWR severe accident scenarios, involving a relocation of corium (core melt)...
International audienceIn PWR severe accident scenarios, involving a relocation of corium (core melt)...
International audienceIn PWR severe accident scenarios, involving a relocation of corium (core melt)...
Pressurized thermal shock experiments are performed in the Prometey Institute for the purpose of inv...
International audienceIn PWR severe accident scenarios, involving a relocation of corium (core melt)...
We describe the model developed for integrity assessment of a reactor pressure vessel (RPV) subjecte...
The present work deals with the development of a detailed Finite Element (FE) model of the Atucha II...
In the structural integrity assessment of a pressurized water reactor pressure vessel (RPV) during p...
Comparative analyses have been performed with 3-D finite element (FE) models for a six loop cladded ...
The Reactor Pressure Vessel (RPV) has long been considered one of the most reliable components in Pr...
The considered research activity deals with the application of a chain of numerical codes, in order ...
International audienceIn PWR severe accident scenarios, involving a relocation of corium (core melt)...
International audienceIn PWR severe accident scenarios, involving a relocation of corium (core melt)...
International audienceIn PWR severe accident scenarios, involving a relocation of corium (core melt)...
International audienceIn PWR severe accident scenarios, involving a relocation of corium (core melt)...
International audienceIn PWR severe accident scenarios, involving a relocation of corium (core melt)...
International audienceIn PWR severe accident scenarios, involving a relocation of corium (core melt)...
International audienceIn PWR severe accident scenarios, involving a relocation of corium (core melt)...
Pressurized thermal shock experiments are performed in the Prometey Institute for the purpose of inv...
International audienceIn PWR severe accident scenarios, involving a relocation of corium (core melt)...