International audienceFormation and destruction of thermal stratification can occur under certain flow conditions in the upper plenum of sodium cooled fast breeder reactors (SFR). The flow patterns in the hot sodium pool of SFR upper plenum are very complex and include zones of free and wall-bounded jets, recirculation and stagnation areas. The interaction of sodium flow and thermal stratification has been analyzed experimentally at CEA in the SUPERCAVNA facility. The facility consists of a rectangular cavity with heated side walls. The flow is driven by a wall-bounded cold jet at the bottom of the cavity. Experimental data of the temperature distribution inside the cavity are available for steady-state and transient flow conditions. In the...
International audienceThe Euratom Horizon-2020 project European sodium fast reactor safety measures ...
International audienceThermal fatigue is a major problem for liquid metal fast reactors due to the h...
Three-dimensional structures of a vortical flow field and heat transfer characteristics in a partial...
International audienceFormation and destruction of thermal stratification can occur under certain fl...
National audienceFormation and destruction of thermal stratification can occur under certain flow co...
© 2020 American Nuclear Society. Investigating thermal stratification in the upper plenum of a sodiu...
International audienceThe paper presents the numerical analysis of core thermal-hydraulic performed ...
The prediction of flow and heat transfer characteristics of liquid sodium with CFD technology is of ...
A concept of the ERVC (External Reactor Vessel Cooling) can be applied to the Sodium Fast Reactor (S...
This dissertation develops and demonstrates the application of the top-down and bottom-up scaling me...
The sodium-cooled fast reactor (SFR), which is one of the most promising candidates for meeting the ...
Evaluation of accidental sodium leak, combustion, and its thermal consequence is one of the importan...
In this work, the velocity and the temperature of the Sodium coolant inside the ESFR sub-channel wer...
Reactor vessel auxiliary cooling system (RVACS) has been developed to make diverse safety system for...
The thermal-hydraulic code TRACE is currently being extended at the Paul Scherrer Institute (PSI) fo...
International audienceThe Euratom Horizon-2020 project European sodium fast reactor safety measures ...
International audienceThermal fatigue is a major problem for liquid metal fast reactors due to the h...
Three-dimensional structures of a vortical flow field and heat transfer characteristics in a partial...
International audienceFormation and destruction of thermal stratification can occur under certain fl...
National audienceFormation and destruction of thermal stratification can occur under certain flow co...
© 2020 American Nuclear Society. Investigating thermal stratification in the upper plenum of a sodiu...
International audienceThe paper presents the numerical analysis of core thermal-hydraulic performed ...
The prediction of flow and heat transfer characteristics of liquid sodium with CFD technology is of ...
A concept of the ERVC (External Reactor Vessel Cooling) can be applied to the Sodium Fast Reactor (S...
This dissertation develops and demonstrates the application of the top-down and bottom-up scaling me...
The sodium-cooled fast reactor (SFR), which is one of the most promising candidates for meeting the ...
Evaluation of accidental sodium leak, combustion, and its thermal consequence is one of the importan...
In this work, the velocity and the temperature of the Sodium coolant inside the ESFR sub-channel wer...
Reactor vessel auxiliary cooling system (RVACS) has been developed to make diverse safety system for...
The thermal-hydraulic code TRACE is currently being extended at the Paul Scherrer Institute (PSI) fo...
International audienceThe Euratom Horizon-2020 project European sodium fast reactor safety measures ...
International audienceThermal fatigue is a major problem for liquid metal fast reactors due to the h...
Three-dimensional structures of a vortical flow field and heat transfer characteristics in a partial...