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Thermodynamic consequences of hydrogen combustion within a containment of pressurized water reactor

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EN
Abstrakty
EN
Gaseous hydrogen may be generated in a nuclear reactor system as an effect of the core overheating. This creates a risk of its uncontrolled combustion which may have a destructive consequences, as it could be observed during the Fukushima nuclear power plant accident. Favorable conditions for hydrogen production occur during heavy loss-of-coolant accidents. The author used an own computer code, called HEPCAL, of the lumped parameter type to realize a set of simulations of a large scale loss-of-coolant accidents scenarios within containment of second generation pressurized water reactor. Some simulations resulted in high pressure peaks, seemed to be irrational. A more detailed analysis and comparison with Three Mile Island and Fukushima accidents consequences allowed for withdrawing interesting conclusions.
Twórcy
autor
  • Silesian University of Technology, Institute of Thermal Technology, Konarskiego 22, 44-100 Gliwice, Poland, Tomasz.Bury@polsl.pl
Bibliografia
  • [1] PREUßER G., FREUDENSTEIN K.F., REINDERS R.: Concept for the analysis of hydrogen problems in nuclear power plants after accidents. In: Proc. of the OECD/NEA/CSNI Workshop on the Implementation of Hydrogen Mitigation Techniques, Winnipeg, Manitoba 1996, 113–127.
  • [2] OECD/NEA: SOAR on containment thermalhydraulics and hydrogen distribution. Report NEA/CSNI(R)99/16. Paris 1999.
  • [3] DE BOECK B.: Introduction to severe accidents. Especially the containment behaviour. AIB VINCOTTE NUCLEAR report AVN 97/013. See also: http://www.avn.org
  • [4] OECD/NEA: PWR fuel behaviour in design basis accident conditions. Report CSNI86/129, Paris 1986.
  • [5] OECD/NEA: Source term assessment, containment atmosphere control systems and accident consequences. Report CSNI87/135, Paris 1987.
  • [6] FIC A., SKOREK J.: Mathematical model of transient thermal and flow processes in containment of a PWR nuclear reactor. Archiwum Energetyki XXXII(1993), 1-2, 19–32.
  • [7] SKOREK J., SKŁADZIEŃ J.: Thermal analysis of the loss-of-coolant accident within the containment of the WWER-440 and WWER-1000 nuclear reactors. Computer Assisted Mechanics and Engineering Sciences 1(1994), 217–231.
  • [8] BURY T.: Analysis of thermal and flow processes within containments of water nuclear reactors during loss-of-coolant accidents. PhD thesis, Institute of Thermal Technology, Silesian University of Technology, Gliwice 2005.
  • [9] Micro-Simulation Technology. PCTRAN/PWR – Personal Computer Transient Analyzer for a Two-loop PWR. Micro-Simulation Technology, Montville, New Jersey, 2004.
  • [10] Florida Power&Light Company: Final safety analysis report for Turkey Point unit 3 and 4. Biscayne Bay, Florida, 1997.
  • [11] BURY T.: Prediction of hydrogen concentration during LOCA within the VVER 440/213 containment. In: Proc. 2nd Int. Conf. on Contemporary Problems of Thermal Engineering, Ustroń 2004.
  • [12] DENG J., CAO X.W.: A study on evaluating a passive autocatalytic recombiner PAR-system in the PWR large-dry containment. Nuclear Engineering and Design 238(2008), 2554–2560.
Typ dokumentu
Bibliografia
Identyfikator YADDA
bwmeta1.element.baztech-article-BGPK-3455-3226
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