In the Core Degradation Project, the contributions of the IKE mainly concerns the improvements and extensions of models, basic versions of which have been developed in the frame of the national BMBF - project KESS. In this project detailed models have been developed to simulate the main processes in the core during a severe accident in light water reactors. The first part of this report is focused on the interacting processes during quenching, like the embrittlement of the fuel rod cladding and of the refreezed melt, the oxidation of the cladding and the crust as well as the cooling effect due to the rapid vaporization. The improved and extended models have been implemented in the code system KESS and as a frist step of the validation the i...
During the normal operation of a Light Water Reactor (LWR), the fuel–cladding gap may close, as a re...
International audienceHighlights The SCANAIR code is devoted to the study of irradiated fuel rod beh...
Severe accidents (SA) in LWR occur when reactor vessel water decreases and there is no available wat...
In the frame of the research program 1500 844/8 - Training of Scientists of the University of Dresde...
The objective of the QUENCH experimental program at the Karlsruhe Research Center is to investigate ...
In the frame of the terminated CEC research activity the FIPREM code has been further developed and ...
Early core degradation determines the amount of hydrogen generated by cladding oxidation as well as ...
International audienceWithin the framework of the Generation IV Sodium-cooled Fast Reactors (SFR) R ...
The comprehensive understanding of fuel rod behavior and accurate prediction of the lifetime in norm...
International audienceIn case of accident at a nuclear power plant, water sources may not be availab...
To get an improved understanding and knowledge of the processes and phenomena during the late phase ...
The major objectives of the experiment were to investigate the behavior of PWR fuel elements during ...
The accident of Fukushima in Japan in March 2011 highlighted the need of further research on severe ...
The development of the computer code ATHLET-CD is a contribution to the reactor safety research. ATH...
An OECD/NEA-CSNI International Standard Problem (ISP) has been performed on the experimental compari...
During the normal operation of a Light Water Reactor (LWR), the fuel–cladding gap may close, as a re...
International audienceHighlights The SCANAIR code is devoted to the study of irradiated fuel rod beh...
Severe accidents (SA) in LWR occur when reactor vessel water decreases and there is no available wat...
In the frame of the research program 1500 844/8 - Training of Scientists of the University of Dresde...
The objective of the QUENCH experimental program at the Karlsruhe Research Center is to investigate ...
In the frame of the terminated CEC research activity the FIPREM code has been further developed and ...
Early core degradation determines the amount of hydrogen generated by cladding oxidation as well as ...
International audienceWithin the framework of the Generation IV Sodium-cooled Fast Reactors (SFR) R ...
The comprehensive understanding of fuel rod behavior and accurate prediction of the lifetime in norm...
International audienceIn case of accident at a nuclear power plant, water sources may not be availab...
To get an improved understanding and knowledge of the processes and phenomena during the late phase ...
The major objectives of the experiment were to investigate the behavior of PWR fuel elements during ...
The accident of Fukushima in Japan in March 2011 highlighted the need of further research on severe ...
The development of the computer code ATHLET-CD is a contribution to the reactor safety research. ATH...
An OECD/NEA-CSNI International Standard Problem (ISP) has been performed on the experimental compari...
During the normal operation of a Light Water Reactor (LWR), the fuel–cladding gap may close, as a re...
International audienceHighlights The SCANAIR code is devoted to the study of irradiated fuel rod beh...
Severe accidents (SA) in LWR occur when reactor vessel water decreases and there is no available wat...