The CORA-Out-of-pile experiments are part of the international Severe Fuel Damage (SFD) prgram. They should provide information on the damage development of Light Water Reactor (LWR) fuel elements in the temperature range 1200 C to 2400 C. In all tests with the exception of CORA-28 and CORA-29 the cladding was used in the as-received state. Test CORA-28 (BWR) and CORA-29 (PWR) were performed with pre-oxidized bundle components. The pre-oxidation should simulate oxide layers that have formed during normal operation in a reactor. The pre-oxidation was performed in the CORA test facility at 800 C (1073 K) for 2000 s with a steam flow rate of 6 g/s. The resulting oxide layer thickness of the cladding surfaces of test bundle CORA-29 varied betwe...
International audienceCr-coated M5(Framatome) cladding materials are studied and developed within th...
The Fukushima-Daiichi nuclear accident has highlighted the importance of analyzing the meltdown of a...
The main target of the EUROATOM FP7 project "Fuel Qualification Test for SCWR" is to make significan...
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) Program. The...
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...
An OECD/NEA-CSNI International Standard Problem (ISP) has been performed on the experimental compari...
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...
The major objectives of the experiment were to investigate the behavior of PWR fuel elements during ...
Das Verhalten der Unfallsequenz ist durch folgende Schritte gekennzeichnet: 1. Der totale Ausfall al...
Die Quenchexperimente CORA-12, CORA-13 und CORA-17 zeigten ebenso wie die Inpile-Experimente LOFT LP...
SIGLEAvailable from TIB Hannover: ZA 5141(4827) / FIZ - Fachinformationszzentrum Karlsruhe / TIB - T...
International audienceCr-coated M5(Framatome) cladding materials are studied and developed within th...
The Fukushima-Daiichi nuclear accident has highlighted the importance of analyzing the meltdown of a...
The main target of the EUROATOM FP7 project "Fuel Qualification Test for SCWR" is to make significan...
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) Program. The...
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...
An OECD/NEA-CSNI International Standard Problem (ISP) has been performed on the experimental compari...
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...
The major objectives of the experiment were to investigate the behavior of PWR fuel elements during ...
Das Verhalten der Unfallsequenz ist durch folgende Schritte gekennzeichnet: 1. Der totale Ausfall al...
Die Quenchexperimente CORA-12, CORA-13 und CORA-17 zeigten ebenso wie die Inpile-Experimente LOFT LP...
SIGLEAvailable from TIB Hannover: ZA 5141(4827) / FIZ - Fachinformationszzentrum Karlsruhe / TIB - T...
International audienceCr-coated M5(Framatome) cladding materials are studied and developed within th...
The Fukushima-Daiichi nuclear accident has highlighted the importance of analyzing the meltdown of a...
The main target of the EUROATOM FP7 project "Fuel Qualification Test for SCWR" is to make significan...