Risk-Informed Analysis of Accidents at Reactor Facilities with VVER
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An accident with ‘rupture of steam line’ as the initial event was studied for a reactor facility with VVER-1000. A computational analysis was performed of different flow scenarios of an accident with singular and multiple failures of the safety systems. The realization probability and the consequences were evaluated for each accident sequence. The consequences of the accidents are ranked and the most instructive combinations of failures of systems and blockings are determined from the standpoint of risk. The presented method is based on multivariate calculations and an integrated combination of deterministic and probabilistic approaches to safety validation.
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- 1.GOST R 51897–2001, Risk Management. Terms and Definitions, Standartinform, Moscow (2012).Google Scholar
- 2.GOST R 51901-2002, Reliability Control. Risk Analysis of Technological Systems, Gosstandart Rossii, Mosow (2002).Google Scholar
- 3.A Framework for an Integrated Risk Informed Decision Making Process, INSAG-25, IAEA, Vienna (2011).Google Scholar
- 4.Accident Analysis for Nuclear Power Plants, Saf. Rep. Ser. 23, IAEA, Vienna (2002).Google Scholar
- 5.Deterministic Safety Analysis for Nuclear Power Plants, Spec. Saf. Guide SSG-2, IAEA, Vienna (2009).Google Scholar
- 7.M. A. Bykov, S. I. Zaitsev, Yu. V. Belyaev, et al., “Improvement of computational software system TRAP-97. Taking account of spatial effects in a reactor,” Teploenergetika, No. 1, 48–52 (2006).Google Scholar