Small Break Loss of Coolant Accident (SB LOCA) is one of the most severe transients which may lead to Pressurized Thermal Shock (PTS) on the Reactor Pressure Vessel (RPV) wall. During postulated SB LOCA Emergency Core Cooling (ECC) water is injected into the cold leg, where it mixes with the hot coolant. The mixture of cold and hot coolants flows toward the downcomer. Knowledge of transient temperature distribution in the downcomer is necessary to predict thermal gradients in the structural components of the RPV wall. For the prediction of the temperature fields and heat transfer coefficient between the fluid and wall in the cold leg and the downcomer, reliable computational fluid dynamics (CFD) simulations are needed. To validate CFD model...
Within the European Integrated Project NURESIM, the simulation of PTS is investigated. Some accident...
This paper reports some activity about the Pressurized Thermal Shock (PTS) performed within the Euro...
International audienceThe aging of the reactor pressure vessel (RPV) can be a limiting factor in lif...
Small Break Loss of Coolant Accident (SB LOCA) is one of the most severe transients which may lead t...
The European Platform for NUclear REactor SIMulations, (NURESIM project 2005-2008) addressed the cre...
Pressurized Thermal Shock (PTS) modelling has been identified as one of the most important industria...
Pressurized thermal shock (PTS) modelling has been identified as one of the most important industria...
One work package of the European project NURESIM (2005-2008) was dedicated to the analysis and impro...
Pressurized Thermal Shock (PTS) modelling has been identified as one of the most important industri...
Temperature gradient on the thick Reactor Pressure Vessel (RPV), caused by sudden overcooling events...
International audienceThe aging of the reactor pressure vessel (RPV) can be a limiting factor in lif...
The present PhD Thesis deals with validation and development of CFD models to simulate two-phase flo...
Pressurized Thermal Shock (PTS) is considered as an important issue that challenges the integrity of...
International audienceThe aging of the reactor pressure vessel (RPV) can be a limiting factor for th...
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...
This paper reports some activity about the Pressurized Thermal Shock (PTS) performed within the Euro...
International audienceThe aging of the reactor pressure vessel (RPV) can be a limiting factor in lif...
Small Break Loss of Coolant Accident (SB LOCA) is one of the most severe transients which may lead t...
The European Platform for NUclear REactor SIMulations, (NURESIM project 2005-2008) addressed the cre...
Pressurized Thermal Shock (PTS) modelling has been identified as one of the most important industria...
Pressurized thermal shock (PTS) modelling has been identified as one of the most important industria...
One work package of the European project NURESIM (2005-2008) was dedicated to the analysis and impro...
Pressurized Thermal Shock (PTS) modelling has been identified as one of the most important industri...
Temperature gradient on the thick Reactor Pressure Vessel (RPV), caused by sudden overcooling events...
International audienceThe aging of the reactor pressure vessel (RPV) can be a limiting factor in lif...
The present PhD Thesis deals with validation and development of CFD models to simulate two-phase flo...
Pressurized Thermal Shock (PTS) is considered as an important issue that challenges the integrity of...
International audienceThe aging of the reactor pressure vessel (RPV) can be a limiting factor for th...
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...
This paper reports some activity about the Pressurized Thermal Shock (PTS) performed within the Euro...
International audienceThe aging of the reactor pressure vessel (RPV) can be a limiting factor in lif...