The DISCO test facility at Forschungszentrum Karlsruhe (FZK) has been used to per-form experiments to investigate direct containment heating (DCH) effects during a severe ac-cident in European nuclear power plants, comprising the EPR, the French 1300 MWe plant P’4, the VVER-1000 and the German Konvoi plant. A high-temperature iron-alumina melt is ejected by steam into scaled models of the respective reactor cavities and the containment vessel. Both heat transfer from dispersed melt and combustion of hydrogen lead to contain-ment pressurization. The main experimental findings are presented and critical parameters are identified. In the framework of SARNET part of this experimental data base is subject for a com-mon interpretation work perfor...
In the frame of SARNET, a joint analysis of comparison of lumped parameters code models and results ...
Direct Containment Heating (DCH) experiments have been completed which utilize prototypic core mater...
In a light-water reactor core melt accident, if the reactor pressure vessel (RPV) fails while the re...
The DISCO test facility at Forschungszentrum Karlsruhe (FZK) has been used to perform experiments to...
The DISCO-H Test Facility at Forschungszentrum Karlsruhe was set up to perform scaled experiments th...
Direct Containment Heating (DCH) is a severe reactor accident scenario in which it is postulated tha...
The DISCO-H test facility was used to perform scaled experiments that simulate melt ejection scenari...
In the SARNET Containment topic three issues of severe accident phenomenology are treated which enda...
In some nuclear reactor core melt accidents, a potential exists for molten core debris to be dispers...
In the SARNET Containment topic three issues of severe accident phenomenology are treated which enda...
Models for direct containment heating (DCH) in the CONTAIN code for severe accident analysis have be...
In the CONTAINMENT area of SARNET three issues of severe accident phenomenol-ogy are treated which e...
Combustion codes were applied to reproduce the experimental data from tests which investigate high p...
Two experiments, DCH-3 and DCH-4, were performed at the Surtsey test facility to investigate phenome...
In the course of a postulated severe accident in an NPP, Direct Containment Heating (DCH) may occur ...
In the frame of SARNET, a joint analysis of comparison of lumped parameters code models and results ...
Direct Containment Heating (DCH) experiments have been completed which utilize prototypic core mater...
In a light-water reactor core melt accident, if the reactor pressure vessel (RPV) fails while the re...
The DISCO test facility at Forschungszentrum Karlsruhe (FZK) has been used to perform experiments to...
The DISCO-H Test Facility at Forschungszentrum Karlsruhe was set up to perform scaled experiments th...
Direct Containment Heating (DCH) is a severe reactor accident scenario in which it is postulated tha...
The DISCO-H test facility was used to perform scaled experiments that simulate melt ejection scenari...
In the SARNET Containment topic three issues of severe accident phenomenology are treated which enda...
In some nuclear reactor core melt accidents, a potential exists for molten core debris to be dispers...
In the SARNET Containment topic three issues of severe accident phenomenology are treated which enda...
Models for direct containment heating (DCH) in the CONTAIN code for severe accident analysis have be...
In the CONTAINMENT area of SARNET three issues of severe accident phenomenol-ogy are treated which e...
Combustion codes were applied to reproduce the experimental data from tests which investigate high p...
Two experiments, DCH-3 and DCH-4, were performed at the Surtsey test facility to investigate phenome...
In the course of a postulated severe accident in an NPP, Direct Containment Heating (DCH) may occur ...
In the frame of SARNET, a joint analysis of comparison of lumped parameters code models and results ...
Direct Containment Heating (DCH) experiments have been completed which utilize prototypic core mater...
In a light-water reactor core melt accident, if the reactor pressure vessel (RPV) fails while the re...