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Evaluation of the effectiveness of functioning of the contemporary solutions of the VVER 440 reactor accident localization systems

Identyfikatory
Warianty tytułu
Konferencja
ENERGETYKA 2004 / International Scientific and Technical Conference [3; 2004; Wrocław, Poland]
Języki publikacji
EN
Abstrakty
EN
Safety terms play the most significant role during designing process and exploitation of a nuclear power plant. The safety analysis is conducted according to the definition of the design-basis accident. A scenario of such accident Jn case of a pressurized water reactor usually assumes a rupture of the main pipeline of the primary cooling circuit and a leakage of the coolant into the reactor building. To prevent progression of the accident and potential contamination of the power plant environment the nuclear reactor with all the primary circuit and safety systems are enclosed within a hermetic building of a containment. The whole is often called as the accident localization system. A review of the contemporary constructions of the accident localization systems for the WER 440 nuclear reactors operating near to Polish borders has been done. Simulations of the containment response during the design-basis accident have been realized using a model of thermodynaimc processes taking place within the containment. On the basis of the results of the simulations for a loss-of-coolant accident (LOCA) a comparative analysis of the effectiveness of operation of the considered systems has been carried out. The most interesting outcomes of calculations and conclusions are presented in the paper.
Rocznik
Strony
51--59
Opis fizyczny
Bibliogr. 11 poz.
Twórcy
autor
  • Instytut Techniki Cieplnej, Politechnika Śląska
  • Instytut Techniki Cieplnej, Politechnika Śląska
Bibliografia
  • [1] BOLSMOV L., STRIZHOV V., KISSELEV A., Severv accident codes status and future development. Nuclear Engineering and Design, vol. 173, pp., 1997.
  • [2] BURY T., 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 z.22, t.1 pp. 169-176 , 2002. (in Polish)
  • [3] Database of die International Nuclear Safety Center at www.insc.anl.gov. 2004.
  • [4] FIC A., SKLADZIEN J., BURY T., TKAC A., SZCZUREK J., Simulations of LOCA accident for modernized units of nuclear power plants VVER 440/230, Proceedings of the 11th Symposium of Heat and Mass Transfer, pp. 397-404, 2001. (in Polish)
  • [5] FIC A., SKOREK J., Mathematical model of transient thermal and flow processes in containment of a PWR nuclear reactor, Archiwum Energetyki nr 1-2, pp. 19-32, 1993.
  • [6] LUNDSTROM P., ROUTAMO T., TUOMISTO H., Hydrogen management strategy for the Loviisa NPP. Proceedings of the OECD/NEA/CSNI Workshop on the Implementation of Hydrogen Mitigation Techniques, Winnipeg, pp. 75-96,1996.
  • [7] LUNDSTROM P., TUOMISTO H., Experimental studies of hydrogen behavior in ice condenser containments. Proceedings of the OECD/NEA/CSNI Workshop on the Implementation of Hydrogen Mitigation Techniques, Winnipeg, pp.159-179, 1996.
  • [8] MURANI J., Accident localization .system with jet condensers for VVER 440-230 NPP at Jaslovske Bohunice, Nucelar Engineering and Design, vol. 157, pp. 387-393, 1995.
  • [9] SEHGAL B.R., Accomplishments and challenges of the severe accident research. Nuclear Engineering and Design, vol. 210, pp., 2001.
  • [10] SKOREK J., SKLADZIEN 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 no. 1, pp. 217-231,1994.
  • [11] TECHY Z., LAJTHA G., TAUBNER R., Accident loads for a VVER-440/213 containment. Nuclear Engineering and Design, vol. 157, pp. 375-385, 1995.
Typ dokumentu
Bibliografia
Identyfikator YADDA
bwmeta1.element.baztech-article-BPP1-0057-0006
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