Invariant methods for an ensemble-based sensitivity analysis of a passive containment cooling system of an AP1000 nuclear power plant

Autor: Giancarlo Nicola, Enrico Zio, Francesco Di Maio, Emanuele Borgonovo
Přispěvatelé: Chaire Sciences des Systèmes et Défis Energétiques EDF/ECP/Supélec (SSEC), EDF R&D (EDF R&D), EDF (EDF)-EDF (EDF)-CentraleSupélec-SUPELEC-Ecole Centrale Paris, Laboratoire Génie Industriel - EA 2606 (LGI), CentraleSupélec, Politecnico di Milano [Milan] (POLIMI), Department of Decision Sciences, Bocconi University, Bocconi University [Milan, Italy], Ecole Centrale Paris-Ecole Supérieure d'Electricité - SUPELEC (FRANCE)-CentraleSupélec-EDF R&D (EDF R&D), EDF (EDF)-EDF (EDF)
Rok vydání: 2016
Předmět:
Risk
[SPI.OTHER]Engineering Sciences [physics]/Other
Engineering
UNCERTAINTY ANALYSIS
Ensemble of methods
Beta Method
020209 energy
RISK ANALYSIS
Probability density function
02 engineering and technology
7. Clean energy
RISK ANALYSIS
SENSITIVITY ANALYSIS
UNCERTAINTY ANALYSIS
Industrial and Manufacturing Engineering
law.invention
System model
Thermal hydraulics
[SPI]Engineering Sciences [physics]
symbols.namesake
Invariant sensitivity analysis methods
Control theory
law
0202 electrical engineering
electronic engineering
information engineering
AP1000 Nuclear Power Plant
Delta method
Pearson correlation ratio
Safety
Risk
Reliability and Quality
Applied Mathematics
SENSITIVITY ANALYSIS
ComputingMilieux_MISCELLANEOUS
business.industry
Pressurized water reactor
Mixture model
Pearson product-moment correlation coefficient
Reliability and Quality
symbols
Safety
business
Loss-of-coolant accident
Zdroj: Reliability Engineering and System Safety
Reliability Engineering and System Safety, Elsevier, 2016, 151, pp.12-19. ⟨10.1016/j.ress.2015.10.006⟩
ISSN: 0951-8320
1879-0836
DOI: 10.1016/j.ress.2015.10.006
Popis: International audience; 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.
Databáze: OpenAIRE
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