Add to ORKGThe investigation of thermal-hydraulic phenomena related to reactor transients with accident management measures is the topic of the Transient and Accident Management (TRAM) programme being carried out at the Upper Plenum Test Facility, which allows simulation of the phenomena on a 1:1 scale relative to the dimensions of a pressurized water reactor. The condensation of steam during emergency core cooling water injection from accumulators into the primary system is one of the phenomena studied. It controls the efficiency of accumulator injection in case the high-pressure safety systems fail. Likewise it is of safety relevance in the case of a pressurized thermal shock during cold leg injection. A phenomenological analysis of performed tests ...
Graduation date: 2008Reflux condensation tests examining steam condensation in a PWR steam\ud genera...
Thermal stratification, which has been linked to the occurrence of pressurized thermal shock (PTS), ...
The International Thermonuclear Experimental Reactor (ITER) Vacuum Vessel Pressure Suppression Syste...
The investigation of thermal-hydraulic phenomena related to reactor transients with accident managem...
Direct Contact Condensation between steam and water as well as bubble entrainment below the water su...
Safety is an essential topic in the development process of nuclear power plant. Several Generation I...
One of the most important problems in the light-water nuclear thermal-hydraulics is behaviour of the...
peer reviewedSafety is an essential topic in the development process of nuclear power plant. Several...
The AP1000® advanced reactor passive safety systems are based on natural phenomena to ensure the con...
A preliminary analysis has been performed with ANSYS© Fluent code to support the experimental campai...
In Tokamak-based fusion technology, a considered severe accident issue is inherent to a sudden overp...
Investigations of the thermal-hydraulic behavior of pressurized water reactors under accident condit...
This paper deals with experimental and theoretical analyses of the steam direct condensation at sub-...
Severe accident codes study the thermo-hydraulics of the suppression chamber with a limited numbers ...
International audienceThe aging of the reactor pressure vessel (RPV) can be a limiting factor in lif...
Graduation date: 2008Reflux condensation tests examining steam condensation in a PWR steam\ud genera...
Thermal stratification, which has been linked to the occurrence of pressurized thermal shock (PTS), ...
The International Thermonuclear Experimental Reactor (ITER) Vacuum Vessel Pressure Suppression Syste...
The investigation of thermal-hydraulic phenomena related to reactor transients with accident managem...
Direct Contact Condensation between steam and water as well as bubble entrainment below the water su...
Safety is an essential topic in the development process of nuclear power plant. Several Generation I...
One of the most important problems in the light-water nuclear thermal-hydraulics is behaviour of the...
peer reviewedSafety is an essential topic in the development process of nuclear power plant. Several...
The AP1000® advanced reactor passive safety systems are based on natural phenomena to ensure the con...
A preliminary analysis has been performed with ANSYS© Fluent code to support the experimental campai...
In Tokamak-based fusion technology, a considered severe accident issue is inherent to a sudden overp...
Investigations of the thermal-hydraulic behavior of pressurized water reactors under accident condit...
This paper deals with experimental and theoretical analyses of the steam direct condensation at sub-...
Severe accident codes study the thermo-hydraulics of the suppression chamber with a limited numbers ...
International audienceThe aging of the reactor pressure vessel (RPV) can be a limiting factor in lif...
Graduation date: 2008Reflux condensation tests examining steam condensation in a PWR steam\ud genera...
Thermal stratification, which has been linked to the occurrence of pressurized thermal shock (PTS), ...
The International Thermonuclear Experimental Reactor (ITER) Vacuum Vessel Pressure Suppression Syste...