RELIABILITY ANALYSIS OF PWR REACTOR PROTECTION SYSTEM


Abstract

The aim of this work was to assess the probability of the Westinghouse PWR reactor protection system (RPS) unavailability. The reference facility for which the analysis has been made was Surry Nuclear Power Plant located in the United States. This work includes RPS fault tree development and qualitative analysis using the SAPHIRE code, as well as the uncertainty assessment by applying the Monte Carlo techniques.


Keywords

Reactor Protection System (RPS); Probabilistic Safety Assessment (PSA); Fault Tree Analysis (FTA); SAPHIRE; Monte Carlo Simulation

Borysiewicz M.: Wykorzystanie probabilistycznych analiz bezpieczeństwa (PSA) w tworzeniu wymogów bezpieczeństwa dla elektrowni jądrowych. Raport NCBJ, Warszawa 2010.

Borysiewicz M., Kowal K., Łuszczek K., Potempski S.: Analiza niezawodności wybranych systemów bezpieczeństwa reaktora PWR przy użyciu programu SAPHIRE. Raport wewn. PAA, Warszawa 2013.

IAEA: Development and Application of Level-1 PSA. IAEA, Vienna 2010.

U.S. Nuclear Regulatory Commission: Reactor Safety Study – An assessment of accident risks in U.S. nuclear power plants. U.S. NRC, Washington 1975.

U.S. Nuclear Regulatory Commission: Reliability Study: Westinghouse Reactor Protection System, 1984-1995. U.S. NRC, Washington 1999.

U.S. Nuclear Regulatory Commission: Nuclear Power for Electrical Generation. U.S. NRC, Washington 2012.


Published : 2015-03-31


Kowal, K., & Borysiewicz, M. (2015). RELIABILITY ANALYSIS OF PWR REACTOR PROTECTION SYSTEM. Informatyka, Automatyka, Pomiary W Gospodarce I Ochronie Środowiska, 5(1), 73-79. https://doi.org/10.5604/20830157.1148053

Karol Kowal  k.kowal@ncbj.gov.pl
Narodowe Centrum Badań Jądrowych (NCBJ), Zakład Energetyki Jądrowej  Poland
Mieczysław Borysiewicz 
Narodowe Centrum Badań Jądrowych (NCBJ), Zakład Energetyki Jądrowej  Poland