Modelling of Failing Reactivity Control in PSA for Barsebäck 2
Barsebäck 2 is a 1800 MWth BWR with external main recirculation pumps of ASEA-Atom design taken into operation 1977. In 1985 a filtered vented system (abbr. FILTRA) for the reactor containment was installed. PSA has been performed for the plant since the mid 80’s in different campaigns. The latest model covers Level 1 and Level 2 for power operation together with shut down and start up of the reactor in one PSA-model. All relevant internal events are modelled. Area events are analysed as the conditional probability for core damage given an area event, e.g. fire and flooding. External events are not modelled to full extent and analysis of the outage period is to come during 2004.
KeywordsReactor Pressure Vessel Accident Scenario Decay Heat Reactor Containment Probabilistic Safety Assessment
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