The final report documents the results of experiments performed at the HORUS I and II test facilities within the scope of the BMFT-project no. 1500857/9 'Experimental Investigations of the Thermohydraulic Behaviour of Tubes in Horizontal Steam Generators under accident conditions for NPP with VVER-Reactors'. The experiments aimed to investigate the integral condensate mass flow and it's flow direction in a heater tube of VVER-steam generators under decay heat conditions (two phase flow during SBLOCA). The scientific tasks, the construction of the HORUS test facilities, the instrumentation and the data acquisition system are described first followed by a general representation of the experimental conditions and the experimental run. The resu...
Safety is an essential topic in the development process of nuclear power plant. Several Generation I...
In der vorliegenden Arbeit wird die Kondensation von Wasserdampf im horizontalen Rohr bei Drücken bi...
A post test calculation of the PKL III test A 4.3 using the GRS system code ATHLET MOD 1.0 Cycle E i...
The final report documents the results of experiments performed at the HORUS-II test facility within...
Selected experimental test facilities located in Eastern European Countries have been assessed with ...
In the thermal hydraulic test facility NOKO at the Research Center Juelich, several important compon...
Im Rahmen dieser Arbeit wurde das thermohydraulische Verhalten des Gebaeudekondensators des SWR 1000...
The research in this thesis supports the design of a horizontal tube bundle condenser for passive he...
The report presents experiments which were aimed at studying steam condensation in horizontal respec...
Many innovative reactor concepts for Generation III nuclear power plants use passive safety equipmen...
In the framework of the external verification of the thermohydraulic computer code ATHLET, developed...
To increase the safety as well as the economy of the innovative boiling water reactor SWR 1000 which...
The Department of “Ingegneria Nucleare e Conversioni di Energia ” of the University of Rome “La Sapi...
Of all the nuclear reactors in operation today, light water reactors and pressurized water reactors ...
A horizontal heat exchanger design has been proposed for the Passive Containment Cooling System (PCC...
Safety is an essential topic in the development process of nuclear power plant. Several Generation I...
In der vorliegenden Arbeit wird die Kondensation von Wasserdampf im horizontalen Rohr bei Drücken bi...
A post test calculation of the PKL III test A 4.3 using the GRS system code ATHLET MOD 1.0 Cycle E i...
The final report documents the results of experiments performed at the HORUS-II test facility within...
Selected experimental test facilities located in Eastern European Countries have been assessed with ...
In the thermal hydraulic test facility NOKO at the Research Center Juelich, several important compon...
Im Rahmen dieser Arbeit wurde das thermohydraulische Verhalten des Gebaeudekondensators des SWR 1000...
The research in this thesis supports the design of a horizontal tube bundle condenser for passive he...
The report presents experiments which were aimed at studying steam condensation in horizontal respec...
Many innovative reactor concepts for Generation III nuclear power plants use passive safety equipmen...
In the framework of the external verification of the thermohydraulic computer code ATHLET, developed...
To increase the safety as well as the economy of the innovative boiling water reactor SWR 1000 which...
The Department of “Ingegneria Nucleare e Conversioni di Energia ” of the University of Rome “La Sapi...
Of all the nuclear reactors in operation today, light water reactors and pressurized water reactors ...
A horizontal heat exchanger design has been proposed for the Passive Containment Cooling System (PCC...
Safety is an essential topic in the development process of nuclear power plant. Several Generation I...
In der vorliegenden Arbeit wird die Kondensation von Wasserdampf im horizontalen Rohr bei Drücken bi...
A post test calculation of the PKL III test A 4.3 using the GRS system code ATHLET MOD 1.0 Cycle E i...