In a world where climatic and environmental issues are questioning the energy policies every day, the nuclear energy has to overcome the safety challenges to prevent severe accident and to eventually keep a place in the world future energy mix. In this context the ability to accurately predict the behavior of a PWR nuclear reactor undergoing a severe accident is a key parameter of the dimensioning of the safety systems. This work focuses on a still understudied phenomenon occurring during the most severe accident, the Loss Of Coolant Accident. A LOCA accident is characterized by the appearance of a large break in the PWR primary circuit, inducing the loss of the water coolant and the depressurization of the circuit. This depressurization in...
During a Loss of Coolant Accident (LOCA) in a Pressurized Water Reactor (PWR), caused by a break or ...
International audienceA dispersed flow of steam and droplets is formed inside the core of a pressuri...
International audienceDuring a loss of coolant accident (LOCA), in a nuclear-pressurized water react...
International audienceDuring a Loss of Coolant Accident (LOCA) in a Pressurized Water Reactor (PWR),...
An appropriate model to predict the size of the droplets resulting from the break-up with the struct...
International audienceThis study focuses on the coolability of a partially deformed fuel assembly of...
International audienceDuring a Loss of Coolant Accident (LOCA) in a Pressurized Water Reactor, parti...
This thesis describes work relating to the reflood phase of a Large Break Loss-of-Coolant Accident (...
International audienceDuring hypothetical Loss of coolant accident in a PWR caused by a large break ...
In a pressurized water reactor (PWR), during a Loss Of Coolant Accident (LOCA), liquid water evapora...
Pressurized water reactor loss-of-coolant accident (LOCA) phenomena are being simulated with a serie...
During a Loss of Coolant Accident (LOCA) in a Pressurized Water Reactor (PWR), caused by a break or ...
International audienceA dispersed flow of steam and droplets is formed inside the core of a pressuri...
International audienceDuring a loss of coolant accident (LOCA), in a nuclear-pressurized water react...
International audienceDuring a Loss of Coolant Accident (LOCA) in a Pressurized Water Reactor (PWR),...
An appropriate model to predict the size of the droplets resulting from the break-up with the struct...
International audienceThis study focuses on the coolability of a partially deformed fuel assembly of...
International audienceDuring a Loss of Coolant Accident (LOCA) in a Pressurized Water Reactor, parti...
This thesis describes work relating to the reflood phase of a Large Break Loss-of-Coolant Accident (...
International audienceDuring hypothetical Loss of coolant accident in a PWR caused by a large break ...
In a pressurized water reactor (PWR), during a Loss Of Coolant Accident (LOCA), liquid water evapora...
Pressurized water reactor loss-of-coolant accident (LOCA) phenomena are being simulated with a serie...
During a Loss of Coolant Accident (LOCA) in a Pressurized Water Reactor (PWR), caused by a break or ...
International audienceA dispersed flow of steam and droplets is formed inside the core of a pressuri...
International audienceDuring a loss of coolant accident (LOCA), in a nuclear-pressurized water react...