Simulations of loos-of-coolant accidents for containments of the second and the third PWR generation

• Autorzy: Bury T. , Składzień J.
• Języki publikacji: EN

Abstrakty

EN

The work deals with modeling of thermal-hydraulic processes taking place within a containment of a pressurized water reactor (PWR) during the Loss-of-Coolant Accident - LOCA. Aim of the work is to compare thermodynamic consequences of the LOCA within containment.s of pressurized water reactors of the second and the third generation types. Simulations have been conducted for the two-loop Westinghouse PWR and for design data of the AP-600 reactor. Calculations have been realized using a computer code HEPCAL-AU worked out at the Institute of Thermal Technology of the Silesian University of Technology, and using the PWR reactor simulator made by the Cassiopeia Technologies. A set of multi-variant simulations for different accident scenarios have been accomplished. Based on the obtained results the analysis of the effectiveness of functioning of the considered systems has been done. The selected results of calculations and the most important conclusions are presented in the paper.

Słowa kluczowe

EN

computer simulations; containment system; LOCA; pressurized water reactor (PWR)

PL

awaria utraty chłodziwa; reaktor wodno-ciśnieniowy; symulacja komputerowa; układ obudowy bezpieczenstwa

• Wydawca: Wydawnictwo Instytutu Maszyn Przepływowych PAN ; Komitet Termodynamiki i Spalania PAN
• Czasopismo: Archives of Thermodynamics
• Rocznik: 2006
• Tom: Vol. 27, no. 4
• Strony: 45--56
• Opis fizyczny: Rys., wykr.,Bibliogr. 7 poz.,

Twórcy

autor

Bury T.

autor

Składzień J.

• Institute of Thermal Technology, Silesian University of Technology, Konarskiego 22, 44-101 Gliwice, Poland

Bibliografia

• [1] Status of advanced light water reactor designs 2004, International Atomic Energy Agency, TecDoc No. 1391, IAEA, Vienna 2004.
• [2] Pressurized water reactor simulator. Workshop material, International Atomic Energy Agency, Training course series No. 22, Vienna 2003.
• [3] 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.
• [4] FIC A., SKOREK J.: Mathematical model of transient thermal and flow processes in containment of a PWR nuclear reactor, Archiwum Energetyki, Vol. 1-2, 1993.
• [5] 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 Vol. 1 No. 3/4, 1994.
• [6] SKŁADZIEŃ J., SKOREK J., FIC A.: Modeling of thermal and flow processes within containments of the VVER type reactors during LOCA, Proceedings of the workshop on the Mathematical Modeling in Energy Systems and Processes, Energy and Environment Protection, Sosnówka-Gliwice, 1995. (in Polish)
• [7] State-of-the-art report on containment thermal-hydraulics and hydrogen distribution, OECD/NEA, CSNI, Paris 1999.