Add to ORKGThe main objectives of the THARE project are to develop and validate calculation methods for safety evaluation of nuclear power plants. The CCFL model of the APROS code has been validated with the IVO upper tie plate experiments. The analysis capabilities of APROS have been verified with the integral OECD/ROSA and OECD/PSB-VVER experiments. TRACE code validation has been started with creating a model of ROSA/LSTF test facility. Containment analysis methods have been enhanced by developing and validating a wall condensation model in Fluent CFD code and by validating the spray model of the APROS code
APROS simulation environment is able to describe the1-D and 3-D neutronics of the reactor core. It i...
Thermal-hydraulics is one of the fundamental disciplines for the design and the operation of water c...
APROS - Advanced PROcess Simulator - has been developed since 1986 together with the Technical Resea...
The main objectives of the THARE project are to develop and validate calculation methods for safety ...
Calculation methods for evaluating safety of nuclear power plants has been enhanced by developing an...
The upper tie plate countercurrent flow limitation correlation of APROS was validated against experi...
An experiment of steam and helium injection and mixing, stratification and helium enrichment due to ...
Thermal hydraulic modelling is needed for describing processes that use water for cooling. Simulator...
Experimental results obtained at integral test facilities are used in the validation process of ther...
The Apros CONtainment model library (ACON) is an add-on product of the Apros ® (Advanced Process Si...
International audienceThe THINS project of the 7th Framework EU Program on nuclear fission safety is...
The integrity of the containment will be challenged during a severe accident due to pressurization c...
The containment of a nuclear reactor is a component whose loss in an accident has serious consequenc...
The European Commission fourth framework programme project ‘Assessment of passive safety injection s...
The thermal hydraulic system analysis code APROS was validated by calculating PATEL NCg, PKL and ROS...
APROS simulation environment is able to describe the1-D and 3-D neutronics of the reactor core. It i...
Thermal-hydraulics is one of the fundamental disciplines for the design and the operation of water c...
APROS - Advanced PROcess Simulator - has been developed since 1986 together with the Technical Resea...
The main objectives of the THARE project are to develop and validate calculation methods for safety ...
Calculation methods for evaluating safety of nuclear power plants has been enhanced by developing an...
The upper tie plate countercurrent flow limitation correlation of APROS was validated against experi...
An experiment of steam and helium injection and mixing, stratification and helium enrichment due to ...
Thermal hydraulic modelling is needed for describing processes that use water for cooling. Simulator...
Experimental results obtained at integral test facilities are used in the validation process of ther...
The Apros CONtainment model library (ACON) is an add-on product of the Apros ® (Advanced Process Si...
International audienceThe THINS project of the 7th Framework EU Program on nuclear fission safety is...
The integrity of the containment will be challenged during a severe accident due to pressurization c...
The containment of a nuclear reactor is a component whose loss in an accident has serious consequenc...
The European Commission fourth framework programme project ‘Assessment of passive safety injection s...
The thermal hydraulic system analysis code APROS was validated by calculating PATEL NCg, PKL and ROS...
APROS simulation environment is able to describe the1-D and 3-D neutronics of the reactor core. It i...
Thermal-hydraulics is one of the fundamental disciplines for the design and the operation of water c...
APROS - Advanced PROcess Simulator - has been developed since 1986 together with the Technical Resea...