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Tytuł artykułu

Methods for the treatment of common cause failures in redundant systems

Treść / Zawartość
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Warianty tytułu
Języki publikacji
EN
Abstrakty
EN
Dependent failures are extremely important in reliability analysis and must be given adequate treatment so as to minimize gross underestimation of reliability. German regulatory guidance documents for PSA stipulate that model parameters used for calculating frequencies should be derived from operating experience in a transparent manner. Progress has been made with the process oriented simulation (POS) model for common cause failure (CCF) quantification. A number of applications are presented for which results obtained from established CCF models are available, focusing on cases with high degree of redundancy and small numbers of observed events.
Rocznik
Tom
Strony
1--8
Opis fizyczny
Bibliogr. 13 poz., rys., tab., wykr.
Twórcy
autor
  • Bundesamt für Strahlenschutz, Salzgitter, Germany
autor
  • Bundesamt für Strahlenschutz, Salzgitter, Germany
autor
  • Bundesamt für Strahlenschutz, Salzgitter, Germany
Bibliografia
  • [1] Berg, H.-P. et al. (1996). Status of Common Cause Failure Analyses in PSA in Germany. Proc. International Topical Meet Probabilistic Safety Assessment, PSA ’96, Park City, Sept 29 – Oct 3, La Grange Park: ANS, 777-782.
  • [2] Berg, H.P. & Görtz, R. (1998). Regulatory Guidance on PSA in Germany, Kerntechnik Vol. 63 (No. 5-6): 278-281.
  • [3] Berg, H.-P. & Görtz, R. (2001). A Model for Common Cause Failures in systems of redundant components. Proc KONBiN‘01, Szczyrk, May, 22 - 25, 2001. Warszawa: Wydaw. Inst. Tech. Wojsk Lotn. Vol. 3: 7-15.
  • [4] Berg, H.-P., Görtz, R. & Schimetschka, E. (2004). Parameter Estimation for the Process Oriented Simulation (POS) Model for Common Cause Failures. Proc. PSAM 7 – ESREL ’04, Berlin, June, 14-18, 2004. London: Springer: 837–842.
  • [5] Berg, H.-P., et al. (2006). Calculating Alpha-Factors with the Process-oriented Simulation Model. Proceedings PSAM 8, New Orleans 2006.
  • [6] Bundesministerium für Umwelt, Naturschutz und Reaktorsicherheit (BMU) (2005). Safety Review for NPP According to § 19a of the Atomic Energy Act - Probabilistic Safety Assessment Guide (Sicherheitsüberprüfung für Kernkraftwerke gemäß §19a des Atomgesetzes – Leitfaden Probabilistische Sicherheitsanalyse, 31. Januar 2005, Bekanntmachung vom 30. August 2005), Bundesanzeiger Nr. 207a vom 03. November 2005.
  • [7] Facharbeitskreis Probabilistische Sicherheits-analyse für Kernkraftwerke (2005). Methods for PSA for NPPs, (Methoden zur probabilistischen Sicherheitsanalyse für Kernkraftwerke, Stand: August 2005), BfS-SCHR – 37/05, Salzgitter, Oktober 2005.
  • [8] Hauptmanns, U. (1996). The Multi-Class Binomial Failure Rate Model. Reliability Eng and Syst Safety Vol. 53 (No. 1): 85-90.
  • [9] Knips, K. & Kreuser, A. (1997). GVA-Benchmark. Schriftenreihe Reaktorsicherheit und Strahlenschutz BMU-1998-514. Bonn: Der Bundesminister für Umwelt, Naturschutz und Reaktorsicherheit.
  • [10] Kreuser, A. & Peschke, J. (2001). Coupling Model: a Common Cause Failures Model with Consideration of Interpretation Uncertainties, Nuclear Technology, Vol. 136, 255-260, December 2001.
  • [11] Kullback, S. (1951). Annals of Math Statist, Vol. 22: 79-84.
  • [12] Marshall, F. M., Rasmuson, D. M. & Mosleh, A. (1998). Common-Cause Failure Parameter Estimations, Washington DC: US Nuclear Regulatory Commission, NUREG/CR-5497.
  • [13] Mosleh, A. Rasmuson, D.M. & Marshall, F.M. (1998). Common - Cause Failures in Probabilistic Risk Assessment. NUREG/CR - 5485 (INEEL/ EXT-97-01327), US Nuclear Regulatory Commission, Washington DC
Typ dokumentu
Bibliografia
Identyfikator YADDA
bwmeta1.element.baztech-2c901f64-6f46-4e69-a28e-105acff14843
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