The work in this project was carried out by 11 European Organisations within the 4th Framework EU Program on Nuclear Fission Safety. The main objectives if this project were to: - develop the capability of calculating the behaviour within a reactor vessel during a severe accident up to vessel melt-through so that the efficacy of accident management strategies can be assessed - understand how accurate the results of such calculations are. The project started in February 1996 and lasted for 3 years It was divided into four main work packages: - development of codes so that the can better represent reactor sequences. - execution of experiments that can be used for the calibration and validation of codes used for reactor sequences. - validation that codes are able to calculate experiments. Some of the experiments used are performed as part of this project. Others are the heritage of past programmes. - scaling studies to make sure that the experiments carried out in this projectrepresent as well as possible phenomena expected to be encountered in reactors.

Investigation of Core Degradation (COBE). Final Report

Ederli, S.;Bandini, G.
1999-07-01

Abstract

The work in this project was carried out by 11 European Organisations within the 4th Framework EU Program on Nuclear Fission Safety. The main objectives if this project were to: - develop the capability of calculating the behaviour within a reactor vessel during a severe accident up to vessel melt-through so that the efficacy of accident management strategies can be assessed - understand how accurate the results of such calculations are. The project started in February 1996 and lasted for 3 years It was divided into four main work packages: - development of codes so that the can better represent reactor sequences. - execution of experiments that can be used for the calibration and validation of codes used for reactor sequences. - validation that codes are able to calculate experiments. Some of the experiments used are performed as part of this project. Others are the heritage of past programmes. - scaling studies to make sure that the experiments carried out in this projectrepresent as well as possible phenomena expected to be encountered in reactors.
Analisi sistemi e di sicurezza
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Utilizza questo identificativo per citare o creare un link a questo documento: http://hdl.handle.net/20.500.12079/6283
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