Sensitivity analysis for CORSOR models simulating fission product release in LOFT-LP-FP-2 severe accident experiment
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S. M. Hoseyni
Abstract
This paper deals with simulation, sensitivity and uncertainty analysis of LP-FP-2 experiment of LOFT test facility. The test facility simulates the major components and system response of a pressurized water reactor during a LOCA. MELCOR code is used for predicting the fission product release from the core fuel elements in LOFT LP-FP-2 experiment. Moreover, sensitivity and uncertainty analysis is performed for different CORSOR models simulating release of fission products in severe accident calculations for nuclear power plants. The calculated values for the fission product release are compared under different modeling options to the experimental data available from the experiment. In conclusion, the performance of 8 CORSOR modeling options is assessed for available modeling alternatives in the code structure.
Kurzfassung
Dieser Beitrag handelt von der Sensitivitäts- und Unsicherheitsanalyse des LP-FP-2-Experiments der LOFT-Versuchsanlage. Die Anlage bildet die Hauptkomponenten und das Systemverhalten eines Druckwasserreaktors während eines LOCA nach. Der MELCOR-Code berechnet die Spaltproduktfreisetzung aus den Kernbrennelementen beim LOFT LP-FP-2-Experiment. Des Weiteren werden Sensitivitäts- und Unsicherheitsanalysen für verschiedene CORSOR-Modelle durchgeführt, die die Spaltproduktfreisetzung bei Unfallrechnungen von Kernkraftwerken simulieren. Die berechneten Werte der Spaltproduktfreisetzung werden unter verschiedenen Modelloptionen verglichen mit den verfügbaren experimentellen Daten. Insgesamt wird die Leistungsfähigkeit von 8 CORSOR-Modell-Optionen bewertet.
References
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© 2017, Carl Hanser Verlag, München
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Articles in the same Issue
- Contents/Inhalt
- Contents
- Summaries/Kurzfassungen
- Summaries
- Technical Contributions/Fachbeiträge
- CANDU pressure tube leak detection by annulus gas dew point measurement: a critical review
- Multiple regression approach to predict turbine-generator output for Chinshan nuclear power plant
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- Development of a parallel processing couple for calculations of control rod worth in terms of burn-up in a WWER-1000 reactor
- Simulation of protected and unprotected loss of flow transients in a WWER-1000 reactor based on the Drift-Flux Model
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- Analysis of the optimal fuel composition for the Indonesian experimental power reactor
- Radiogenic lead from poly-metallic thorium ores as a valuable material for advanced nuclear facilities
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- Font Attributes based Text Steganographic algorithm (FATS) for communicating images: A nuclear power plant perspective
- Size control synthesis and characterization of ZnO nanoparticles and its application as ZnO-water based nanofluid in heat transfer enhancement in light water nuclear reactor
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