This paper reports some activity about the Pressurized Thermal Shock (PTS) performed within the European Integrated Project NURESIM. The PTS phenomenon is expected to take place in some water cooled nuclear reactors equipped with pressure vessels during selected accident scenarios. The PTS implies the formation of temperature gradients in the thick vessel walls with consequent localized stresses and the potential for propagation of possible flaws present in the material. Current generation Pressurized Water Reactors, PWR (including the Russian VVER types), are primarily affected by the phenomenon which is investigated within three broad areas: material damage originated by irradiation, thermal-hydraulics (including single and two-phase flow...
In order to investigate the two-phase flow behaviour in a complex reactor-typical geometry and to su...
We describe the model developed for integrity assessment of a reactor pressure vessel (RPV) subjecte...
In the structural integrity assessment of a pressurized water reactor pressure vessel (RPV) during p...
This paper reports some activity about the Pressurized Thermal Shock (PTS) performed within the Euro...
Within the European Integrated Project NURESIM, the simulation of PTS is investigated. Some accident...
Within the European Integrated Project NURESIM, the simulation of PTS is investigated. Some accident...
The European Platform for NUclear REactor SIMulations, (NURESIM project 2005-2008) addressed the cre...
One work package of the European project NURESIM (2005-2008) was dedicated to the analysis and impro...
International audienceSmall Break Loss of Coolant Accident (SB LOCA) is one of the most severe trans...
The present PhD Thesis deals with validation and development of CFD models to simulate two-phase flo...
This report summarizes the results of the NURESIM project for the work package 2.1 “Pressurized Ther...
Pressurized thermal shock experiments are performed in the Prometey Institute for the purpose of inv...
The present work deals with the application of single-phase and two-phase Computational Fluid Dynami...
High neutron flux in core of a nuclear reactor can affect the material of Reactor Pressure Vessel (R...
International audienceThe aging of the reactor pressure vessel (RPV) can be a limiting factor for th...
In order to investigate the two-phase flow behaviour in a complex reactor-typical geometry and to su...
We describe the model developed for integrity assessment of a reactor pressure vessel (RPV) subjecte...
In the structural integrity assessment of a pressurized water reactor pressure vessel (RPV) during p...
This paper reports some activity about the Pressurized Thermal Shock (PTS) performed within the Euro...
Within the European Integrated Project NURESIM, the simulation of PTS is investigated. Some accident...
Within the European Integrated Project NURESIM, the simulation of PTS is investigated. Some accident...
The European Platform for NUclear REactor SIMulations, (NURESIM project 2005-2008) addressed the cre...
One work package of the European project NURESIM (2005-2008) was dedicated to the analysis and impro...
International audienceSmall Break Loss of Coolant Accident (SB LOCA) is one of the most severe trans...
The present PhD Thesis deals with validation and development of CFD models to simulate two-phase flo...
This report summarizes the results of the NURESIM project for the work package 2.1 “Pressurized Ther...
Pressurized thermal shock experiments are performed in the Prometey Institute for the purpose of inv...
The present work deals with the application of single-phase and two-phase Computational Fluid Dynami...
High neutron flux in core of a nuclear reactor can affect the material of Reactor Pressure Vessel (R...
International audienceThe aging of the reactor pressure vessel (RPV) can be a limiting factor for th...
In order to investigate the two-phase flow behaviour in a complex reactor-typical geometry and to su...
We describe the model developed for integrity assessment of a reactor pressure vessel (RPV) subjecte...
In the structural integrity assessment of a pressurized water reactor pressure vessel (RPV) during p...