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Modelling of Failing Reactivity Control in PSA for Barsebäck 2

  • Ingemar Ingemarson
  • Lars Olsson
  • Ola Bäckström
Conference paper

Abstract

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.

Keywords

Reactor Pressure Vessel Accident Scenario Decay Heat Reactor Containment Probabilistic Safety Assessment 
These keywords were added by machine and not by the authors. This process is experimental and the keywords may be updated as the learning algorithm improves.

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References

  1. 1.
    Mankamo, T. Common Cause Failure Analysis of Hydraulic Scram and Control Rod Systems in the Swedish and Finnish BWR Plants, December 1996, SKI Report 96: 77Google Scholar

Copyright information

© Springer-Verlag London 2004

Authors and Affiliations

  • Ingemar Ingemarson
    • 1
  • Lars Olsson
    • 1
  • Ola Bäckström
    • 2
  1. 1.Ringhals AB — BarsebäcksverketLöddeköpingeSweden
  2. 2.RELCON ABSundbybergSweden

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