Following a long-lasting failure in the cooling system of a pressurized water reactor (PWR), the superheated core can be efficiently cooled down by reflooding. The macroscopic model used at the French Institute of Radioprotection and Nuclear Safety (IRSN) to simulate this process is based on strong assumptions on the microscopic flow patterns. This paper describes the experimental setup designed for the study of boiling in porous media with the emphasis on various pore-scale boiling regimes. The final experimental setup is a two-dimensional porous medium made of 392 cylinders randomly placed between two ceramic plates. Each heating cylinder is a RTD probe (Resistance Temperature Detector), that can give thermal measurements in every point ...
International audienceDuring an hypothetical reactivity initiated accident in the core of a nuclear ...
International audienceDryout experiments are performed in a quasi two-dimensional heat-generating mo...
International audienceIn case of accident at a nuclear power plant, water sources may not be availab...
Following a long-lasting failure in the cooling system of a water reactor, the superheated core can ...
Following a long-lasting failure in the cooling system of a pressurized water reactor (PWR), the sup...
International audienceThis paper presents a pore-scale experimental study of the reflooding of a two...
International audienceFollowing a loss of coolant accident in a nuclear reactor, the materials of th...
This manuscript presents a pore-scale experimental study of convective boiling heat transfer in a tw...
Following a loss of coolant accident in a nuclear reactor, the materials of the core can crumble and...
Ce travail propose une étude expérimentale de l'ébullition en masse dans une structure poreuse modè...
Porous Media, Two-Phase Flow, In-Vessel Coolability The research activities presented concentrate on...
The objective of this work is to improve the understanding of the process of boiling in porous media...
To evaluate the effects of porous deposits over a heating surface on the boiling heat transfer in li...
International audienceDuring an hypothetical reactivity initiated accident in the core of a nuclear ...
International audienceDryout experiments are performed in a quasi two-dimensional heat-generating mo...
International audienceIn case of accident at a nuclear power plant, water sources may not be availab...
Following a long-lasting failure in the cooling system of a water reactor, the superheated core can ...
Following a long-lasting failure in the cooling system of a pressurized water reactor (PWR), the sup...
International audienceThis paper presents a pore-scale experimental study of the reflooding of a two...
International audienceFollowing a loss of coolant accident in a nuclear reactor, the materials of th...
This manuscript presents a pore-scale experimental study of convective boiling heat transfer in a tw...
Following a loss of coolant accident in a nuclear reactor, the materials of the core can crumble and...
Ce travail propose une étude expérimentale de l'ébullition en masse dans une structure poreuse modè...
Porous Media, Two-Phase Flow, In-Vessel Coolability The research activities presented concentrate on...
The objective of this work is to improve the understanding of the process of boiling in porous media...
To evaluate the effects of porous deposits over a heating surface on the boiling heat transfer in li...
International audienceDuring an hypothetical reactivity initiated accident in the core of a nuclear ...
International audienceDryout experiments are performed in a quasi two-dimensional heat-generating mo...
International audienceIn case of accident at a nuclear power plant, water sources may not be availab...