Invariant methods for an ensemble-based sensitivity analysis of a passive containment cooling system of an AP1000 nuclear power plant. (July 2016)

• Record Type: Journal Article
• Authors: Di Maio, Francesco; Nicola, Giancarlo; Borgonovo, Emanuele; Zio, Enrico
• Is Part Of: Reliability engineering & system safety. Volume 151(2016:Jul.)
• Page Start: 12
• Page End: 19
• Publication Date: 2016-07
• Subjects: Invariant sensitivity analysis methods -- Pearson correlation ratio -- Delta method -- Beta Method -- AP1000 Nuclear Power Plant -- Ensemble of methods; Reliability (Engineering) -- Periodicals; System safety -- Periodicals; Industrial safety -- Periodicals; Fiabilité -- Périodiques; Sécurité des systèmes -- Périodiques; Sécurité du travail -- Périodiques; 620.00452
• DOI: 10.1016/j.ress.2015.10.006
• Languages: English
• ISSNs: 0951-8320

Abstract

Abstract: Sensitivity Analysis (SA) is performed to gain fundamental insights on a system behavior that is usually reproduced by a model and to identify the most relevant input variables whose variations affect the system model functional response. For the reliability analysis of passive safety systems of Nuclear Power Plants (NPPs), models are Best Estimate (BE) Thermal Hydraulic (TH) codes, that predict the system functional response in normal and accidental conditions and, in this paper, an ensemble of three alternative invariant SA methods is innovatively set up for a SA on the TH code input variables. The ensemble aggregates the input variables raking orders provided by Pearson correlation ratio, Delta method and Beta method. The capability of the ensemble is shown on a BE–TH code of the Passive Containment Cooling System (PCCS) of an Advanced Pressurized water reactor AP1000, during a Loss Of Coolant Accident (LOCA), whose output probability density function (pdf) is approximated by a Finite Mixture Model (FMM), on the basis of a limited number of simulations. Highlights: We perform the reliability analysis of a passive safety system of Nuclear Power Plant (NPP). We use a Thermal Hydraulic (TH) code for predicting the NPP response to accidents. We propose an ensemble of Invariant Methods for the sensitivity analysis of the TH code The ensemble aggregates the rankings of Pearson correlation, Delta and Beta methods. The approach is tested on a Passive Containment Cooling System of an AP1000 NPP.