The CORA out-of-pile experiments are part of the international Severe Fuel Damage (SFD) Program. They were performed to provide information on the damage progression of Light Water Reactor (LWR) fuel elements in Loss-of-coolant Accidents in the temperature range 1200 C to 2400 C. CORA-18 was the large BWR bundle test corresponding to the PWR test CORA-7. It should investigate if there exists an influence of the BWR bundle size on the fuel damage behaviour. Therefore, the standard-type BWR CORA bundle with 18 fuel rod simulators was replaced by a large bundle with two additional surrounding rows of 30 rods (48 rods total). Power input and steam flow were increased proportionally to the number of fuel rod simulators to give the same initial h...
The objective of the QUENCH experimental program at the Karlsruhe Research Center is to investigate ...
Im CORA-Versuchsprogramm des Kernforschungszentrums Karlsruhe (KfK) wird das Brennelementverhalten b...
Under the scope of international "Sever Fuel Damage (SFD)" program, Cora experiments are actualized ...
Die CORA-Out-of-pile-Experimente wurden im Rahmen des internationalen 'Severe Fuel Damage' Programms...
The CORA out-of-pile experiments are part of the international Severe Fuel Damage (SFD) Program. The...
The CORA out-of-pile experiments were part of the international Severe Fuel Damage (SFD) program. Th...
The CORA-Out-of-pile experiments are part of the international Severe Fuel Damage (SFD) prgram. They...
The PWR-type assemblies usually consist of 25 rods with 16 electrically heated fuel rod simulators a...
Copy held by FIZ Karlsruhe; available from UB/TIB Hannover / FIZ - Fachinformationszzentrum Karlsruh...
The 'Severe Fuel Damage' (SFD) experiments of the Kernforschungszentrum Karlsruhe (KfK), Federal Rep...
An OECD/NEA-CSNI International Standard Problem (ISP) has been performed on the experimental compari...
Das Verhalten der Unfallsequenz ist durch folgende Schritte gekennzeichnet: 1. Der totale Ausfall al...
The major objectives of the experiment were to investigate the behavior of PWR fuel elements during ...
The Fukushima-Daiichi nuclear accident has highlighted the importance of analyzing the meltdown of a...
Die Quenchexperimente CORA-12, CORA-13 und CORA-17 zeigten ebenso wie die Inpile-Experimente LOFT LP...
The objective of the QUENCH experimental program at the Karlsruhe Research Center is to investigate ...
Im CORA-Versuchsprogramm des Kernforschungszentrums Karlsruhe (KfK) wird das Brennelementverhalten b...
Under the scope of international "Sever Fuel Damage (SFD)" program, Cora experiments are actualized ...
Die CORA-Out-of-pile-Experimente wurden im Rahmen des internationalen 'Severe Fuel Damage' Programms...
The CORA out-of-pile experiments are part of the international Severe Fuel Damage (SFD) Program. The...
The CORA out-of-pile experiments were part of the international Severe Fuel Damage (SFD) program. Th...
The CORA-Out-of-pile experiments are part of the international Severe Fuel Damage (SFD) prgram. They...
The PWR-type assemblies usually consist of 25 rods with 16 electrically heated fuel rod simulators a...
Copy held by FIZ Karlsruhe; available from UB/TIB Hannover / FIZ - Fachinformationszzentrum Karlsruh...
The 'Severe Fuel Damage' (SFD) experiments of the Kernforschungszentrum Karlsruhe (KfK), Federal Rep...
An OECD/NEA-CSNI International Standard Problem (ISP) has been performed on the experimental compari...
Das Verhalten der Unfallsequenz ist durch folgende Schritte gekennzeichnet: 1. Der totale Ausfall al...
The major objectives of the experiment were to investigate the behavior of PWR fuel elements during ...
The Fukushima-Daiichi nuclear accident has highlighted the importance of analyzing the meltdown of a...
Die Quenchexperimente CORA-12, CORA-13 und CORA-17 zeigten ebenso wie die Inpile-Experimente LOFT LP...
The objective of the QUENCH experimental program at the Karlsruhe Research Center is to investigate ...
Im CORA-Versuchsprogramm des Kernforschungszentrums Karlsruhe (KfK) wird das Brennelementverhalten b...
Under the scope of international "Sever Fuel Damage (SFD)" program, Cora experiments are actualized ...