CATHARE is a 2-fluid thermal-hydraulic system code, capable of simulating phenomena occurring in the primary and secondary circuits of a PWR (Pressurized Water Reactor) under a wide variety of accidental situations. The latest version CATHARE-3 uses a 3D modeling of a PWR core at the assembly scale to simulate various accidental situations such as the loss of coolant accident (LOCA) or the steam line break accident. This requires that the one-phase and two-phase mixing models are adapted to the assembly scale and that every closure law is validated in a separate way. The code models for the 3D turbulent diffusion and dispersion of momentum and energy have been validated at sub-channel scale against experimental data. In this work, the energ...
Nuclear fuel bundles include spacers essentially for mechanical stability and to influence the flow ...
The current generation of thermal-hydraulic system codes benefits of about sixty years of experiment...
International audienceA coolant flow is used in Pressurized-Water Reactors (PWR) cores to extract th...
International audienceCATHARE is a 2-fluid thermal-hydraulic system code, capable of simulating phen...
International audienceCATHARE is a 2-fluid thermal-hydraulic system code, capable of simulating phen...
International audienceCATHARE is a 2-fluid thermal-hydraulic system code, capable of simulating phen...
International audienceCATHARE is a 2-fluid thermal-hydraulic code, capable of simulating thermal and...
International audienceCATHARE-3 is the new version of the French thermal-hydraulic code for the safe...
International audienceCATHARE-3 is the new version of the French thermal-hydraulic code for the safe...
International audienceCATHARE is a 2-fluid thermal-hydraulic code, capable of simulating thermal and...
International audienceCATHARE is a 2-fluid thermal-hydraulic code, capable of simulating thermal and...
International audienceA coolant flow is used in Pressurized-Water Reactors (PWR) cores to extract th...
Accurate prediction of steam volume fraction and of the boiling crisis (either DNB or dryout) occurr...
Accurate prediction of steam volume fraction and of the boiling crisis (either DNB or dryout) occurr...
Accurate prediction of steam volume fraction and of the boiling crisis (either DNB or dryout) occurr...
Nuclear fuel bundles include spacers essentially for mechanical stability and to influence the flow ...
The current generation of thermal-hydraulic system codes benefits of about sixty years of experiment...
International audienceA coolant flow is used in Pressurized-Water Reactors (PWR) cores to extract th...
International audienceCATHARE is a 2-fluid thermal-hydraulic system code, capable of simulating phen...
International audienceCATHARE is a 2-fluid thermal-hydraulic system code, capable of simulating phen...
International audienceCATHARE is a 2-fluid thermal-hydraulic system code, capable of simulating phen...
International audienceCATHARE is a 2-fluid thermal-hydraulic code, capable of simulating thermal and...
International audienceCATHARE-3 is the new version of the French thermal-hydraulic code for the safe...
International audienceCATHARE-3 is the new version of the French thermal-hydraulic code for the safe...
International audienceCATHARE is a 2-fluid thermal-hydraulic code, capable of simulating thermal and...
International audienceCATHARE is a 2-fluid thermal-hydraulic code, capable of simulating thermal and...
International audienceA coolant flow is used in Pressurized-Water Reactors (PWR) cores to extract th...
Accurate prediction of steam volume fraction and of the boiling crisis (either DNB or dryout) occurr...
Accurate prediction of steam volume fraction and of the boiling crisis (either DNB or dryout) occurr...
Accurate prediction of steam volume fraction and of the boiling crisis (either DNB or dryout) occurr...
Nuclear fuel bundles include spacers essentially for mechanical stability and to influence the flow ...
The current generation of thermal-hydraulic system codes benefits of about sixty years of experiment...
International audienceA coolant flow is used in Pressurized-Water Reactors (PWR) cores to extract th...