Add to ORKGCalculation methods for evaluating safety of nuclear power plants has been enhanced by developing and validating both thermal hydraulic system codes APROS and TRACE and models in CFD code Fluent. Several experiments in national and international research programs have been calculated and results have compared with measured data. The validation cases has been chosen according the safety relevance of the studied phenomena and taking in account the specific features of the new plant concepts offered to Finnish utilities
An attempt is made in the Book to provide a vision of nuclear thermal-hydraulics as it appears follo...
A review of industrial needs for at least the next decade was performed and a list of 44 needs was e...
A list of 116 Thermal-Hydraulic Phenomena T-HP is derived in the present paper following documents i...
Calculation methods for evaluating safety of nuclear power plants has been enhanced by developing an...
The main objectives of the THARE project are to develop and validate calculation methods for safety ...
An experiment of steam and helium injection and mixing, stratification and helium enrichment due to ...
Thermal-hydraulics is one of the fundamental disciplines for the design and the operation of water c...
This thesis focuses on the validation of the coupled codes developed in Finland for the safety analy...
Nuclear Reactor Safety (NRS), Deterministic Safety Assessment (DSA) and Accident Analysis (AA) const...
The Best Estimate approach in nuclear thermal-hydraulics has been developed within the framework of ...
International audienceThe THINS project of the 7th Framework EU Program on nuclear fission safety is...
An established international expertise in relation to computational tools, procedures for their app...
The nuclear reactor safety technology is based on Deterministic Safety Analysis (DSA) and Probabilis...
In the last four decades, large efforts have been undertaken to provide reliable thermal-hydraulic s...
Validation of best-estimate codes is a necessary step to prove their applicability to calculate acci...
An attempt is made in the Book to provide a vision of nuclear thermal-hydraulics as it appears follo...
A review of industrial needs for at least the next decade was performed and a list of 44 needs was e...
A list of 116 Thermal-Hydraulic Phenomena T-HP is derived in the present paper following documents i...
Calculation methods for evaluating safety of nuclear power plants has been enhanced by developing an...
The main objectives of the THARE project are to develop and validate calculation methods for safety ...
An experiment of steam and helium injection and mixing, stratification and helium enrichment due to ...
Thermal-hydraulics is one of the fundamental disciplines for the design and the operation of water c...
This thesis focuses on the validation of the coupled codes developed in Finland for the safety analy...
Nuclear Reactor Safety (NRS), Deterministic Safety Assessment (DSA) and Accident Analysis (AA) const...
The Best Estimate approach in nuclear thermal-hydraulics has been developed within the framework of ...
International audienceThe THINS project of the 7th Framework EU Program on nuclear fission safety is...
An established international expertise in relation to computational tools, procedures for their app...
The nuclear reactor safety technology is based on Deterministic Safety Analysis (DSA) and Probabilis...
In the last four decades, large efforts have been undertaken to provide reliable thermal-hydraulic s...
Validation of best-estimate codes is a necessary step to prove their applicability to calculate acci...
An attempt is made in the Book to provide a vision of nuclear thermal-hydraulics as it appears follo...
A review of industrial needs for at least the next decade was performed and a list of 44 needs was e...
A list of 116 Thermal-Hydraulic Phenomena T-HP is derived in the present paper following documents i...