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Proposal for estimating leak and break frequencies of piping systems in probabilistic safety assessment

Treść / Zawartość
Identyfikatory
Warianty tytułu
Języki publikacji
EN
Abstrakty
EN
The estimation of leak and break frequencies in piping systems is part of the probabilistic safety assessment of technical plants. In this paper, the statistical method based on the evaluation of the German operational experience for piping systems with different diameters is described because an earlier estimation has been updated and extended introducing new methodical aspects and data. Major point is the inclusion of structure reliability models based on fracture mechanics calculation procedures. As an example of application the statistical estimation method for leak and break frequencies of piping systems with a nominal diameter of 50 mm (the volume control system of a German pressurized water reactor) was updated. Moreover, the evaluation of the operational experience was extended to 341 years with respect to cracks, leaks and breaks in the volume control system of German pressurized water reactors (PWR). Using the actual data base, new calculations of leak and break frequencies have been performed and the results have been compared with the previous values.
Rocznik
Tom
Strony
33--42
Opis fizyczny
Bibliogr. 22 poz., rys., tab.
Twórcy
autor
  • Bundesamt für Strahlenschutz, Salzgitter, Germany
autor
  • Bundesamt für Strahlenschutz, Salzgitter, Germany
autor
  • Gesellschaft für Anlagen- und Reaktorsicherheit, Köln, Germany
Bibliografia
  • [1] Beliczey, S. & Schulz, H. (1990). Comments on probabilities of leaks and breaks of safety-related piping in PWR plants. Int. J. Pres. Ves. & Piping Vol. 43, 219-227.
  • [2] Beliczey, S. (1995). Grundlegende statistische Methoden. GRS-Fachseminar zu „Ermittlung der Häufigkeiten von Lecks und Brücken in druckführenden Systemen für PSA“, Köln, 18.-20. September 1995 (published in German).
  • [3] Bieniussa, K., Schulz, H., Goetsch, D., & Jalouneix, J. (1995). Integrity of the Reactor Coolant Boundary of the European Pressurized Water Reactor - Requirements for the Application of the Break Precluding Concept to the Main Coolant Lines. Proceedings of the Seminar on Leak-Before-Break in Reactor Piping and Vessels, Lyon. France, October 9-11, 1995. NUREG/CP-0155.
  • [4] Berg, H. P. (2009). Overview on the different applications of probabilistic safety assessment for nuclear power plants. Kerntechnik 74, No 3, 106-110.
  • [5] European Commission. (2000). Final Report: Comparison of National Leak-Before-Break Procedures and Practices - Summary of Results and Potential for Greater Harmonisation. Revision 2, EU Study Contract B7-5200/97/000782/MAR/C2 of DG XI, April 2000.
  • [6] European Commission. (2005). Report on the Regulatory Experience of Risk-informed In-Service Inspection of Nuclear Power Plant Components and Common Views. EUR 21320 EN, August 2004, Luxembourg, 2005.
  • [7] Facharbeitskreis Probabilistische Sicherheitsanalyse für Kernkraftwerke (2005). Methoden zur probabilistischen Sicherheitsanalyse für Kernkraftwerke, Stand: August 2005. BfS-SCHR-37/05, Salzgitter, October 2005 (published in German).
  • [8] Facharbeitskreis Probabilistische Sicherheitsanalyse für Kernkraftwerke (2005). Daten zur probabilistischen Sicherheitsanalyse für Kernkraftwerke, Stand: August 2005. BfS-SCHR-38/05, Salzgitter, October 2005 (published in German).
  • [9] Fleming, K. (2004) Markov models for evaluating risk-informed in-service inspection strategies for nuclear power plant piping systems. Reliability Engineering & Safety System 83, 27-45.
  • [10] Fleming, K. & Lydell, B. (2004). Database development and uncertainty treatment for estimating pipe failure rates and rupturę frequencies. Reliability Engineering & Safety System 86, 227-246.
  • [11] Grebner, H., Schimpfke, T., Peschke, J. & Sievers, J. (2004). Weiterentwicklung der strukturmechanischen Analysemethodik zur Bestimmung der Strukturzuverlässigkeit passiver Komponenten. GRS-A-3236 (published in German).
  • [12] Lydell, B. & Riznic, J. (2008). OPDE – the international pipe failure data exchange project. Nuclear Engineering and Design 238, 8, 2115-2123.
  • [13] Hoffmann, H. et al. (2007). Integrity concept for piping systems with corresponding leak and break postulates in German nuclear power plants. VGB Power Tech 7, 3-16.
  • [14] Nuclear Energy Agency/OECD. (2007). Use and Development of Probabilistic Safety Assessment, NEA/CSNI/R (2007) 12, November 2007.
  • [15] NURBIM (2004). Nuclear Risk-Based Inspection Methodology for Passive Components (NURBIM), 2004. EU Contract FIKS-CT-2001-00172, Final report.
  • [16] Reaktor-Sicherheitskommission RSK (1979). 2. Anhang zu den RSK-Leitlinien für Druckwasserreaktoren 1979. (2. Ausgabe vom 24. Jan. 1979) Kapitel 4.2, Rahmenspezifikation Basissicherheit von druckführenden Komponenten, Stand 25.04.1979.
  • [17] Reaktor-Sicherheitskommission (RSK) (1981). RSK-Leitlinien für Druckwasserreaktoren. Ausgabe 10/1981.
  • [18] Schulz, H. (1995). The Evolution of the Break Preclusion Concept for Nuclear Power Plants in Germany. Proceedings of the Seminar on Leak-Before-Break in Reactor Piping and Vessels. Lyon, France, October 9-11, 1995. NUREG/CP-0155.
  • [19] Simola, K. et al. (2004). Comparison of approaches for estimating pipe rupture frequencies for risk-informed in-service inspections. Reliability Engineering & Safety System 84, 65-74.
  • [20] Spuge, J. (2005). New generic leak frequencies for process equipment. Process Safety Progress 24, No 4, 249-257.
  • [21] Thomas, H. M. (1981). Pipe and Vessel Failure Probability. Rel. Engineering 2., 83-124.
  • [22] U.S. Nuclear Regulatory Commission (2008). Estimating loss-of-coolant accident (LOCA) frequencies through the elicitation process, main report. NUREG-1829, Vol. 1, April 2008.
Typ dokumentu
Bibliografia
Identyfikator YADDA
bwmeta1.element.baztech-d052a676-8f95-40f9-8c6c-5ca9141469f8
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