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Efficiency of selected methods of hydrogen removal from a nuclear reactor's containment building

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Języki publikacji
EN
Abstrakty
EN
Large amounts of gaseous hydrogen may be released into the containment building during a severe accident in a water cooled nuclear reactor. The main methods of hydrogen removal from the containment are described in brief in this paper. HEPCAL - an in-house lumped parameter computer code - was used for simulation purposes and the results were used to evaluate the efficiency of various hydrogen removal systems.
Rocznik
Strony
96--104
Opis fizyczny
Bibliogr. 14 poz., rys., wykr.
Twórcy
autor
  • Institute of Thermal Technology, Silesian University of Technology, Konarskiego 22, 44-100 Gliwice, Poland
Bibliografia
  • [1] International Atomic Energy Agency: Power reactor information system – PRIS. Available at http://www.iaea.org/pris/ - Access on September 29 2013.
  • [2] J. Lamarsh, A. Baratta, Introduction to Nuclear Engineering, Prentice Hall, New York, 2002.
  • [3] De Boeck B., Introduction to severe accidents. Especially the containment behaviour. AIB VINCOTTE NUCLEAR report AVN 97/013.
  • [4] International Atomic Energy Agency: Nuclear Emergency Response Headquarters – Government of Japan: Report of Japanese Government to the IAEA Ministerial Conference on Nuclear Safety. IAEA, Vienna, June 2011.
  • [5] B. Sehgal, Nuclear safety in light water reactors. Severe accident phenomenology, 1st Edition, Elsevier Academic Press, 2012.
  • [6] B. E, A. F., Generic approach for designing and implementing a passive autocatalytic recombiner par system in nuclear power plant containments., Nuclear Engineering and Design 275 (2002) 1–15.
  • [7] International Atomic Energy Agency: Mitigation of hydrogen hazards in water cooled power reactors. IAEATECDoc 1196, Vienna, 2001.
  • [8] T. Bury, Analysis of thermal and flow processes within containments of water nuclear reactors during loss-of coolant accidents, Ph.D. thesis, Institute of Thermal Technology, Silesian University of Technology, Gliwice (2005).
  • [9] A. Fic, J. Skorek, Mathematical model of transient thermal and flow processes in containment of a pwr nuclear reactor, Archiwum Energetyki 1-2 (1993) 19–32.
  • [10] J. Skorek, J. Składzień, 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 (3/4) (1994) 217–231.
  • [11] T. Bury, Influence of the accident localization system construction on the course of the primary circuit rupture accident in vver 440 units, Zeszyty Naukowe Politechniki Warszawskiej, seria Konferencje 1 (2002) 169–176, (in Polish).
  • [12] Z. Techy, G. Lajtha, R. Taubner, Accident loads for vver- 440/213 containment, Nuclear Engineering and Design 157 (1995) 375–385.
  • [13] AREVA: AREVA passive autocatalytic recombiner. Document G-008-V1PB-2011-ENG, AREVA, Paris, 2011.
  • [14] Kostka P., Techy Z. and Sienicki J., Hydrogen mixing analyses for a VVER containment. Proceedings of 10th International Conference on Nuclear Engineering, Arlington, 2002, paper ICONE10-22206.
Typ dokumentu
Bibliografia
Identyfikator YADDA
bwmeta1.element.baztech-a8f339e2-6b2c-4b38-ac07-39fcdc813a94
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