Szczegóły

Tytuł artykułu

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

Tytuł czasopisma

Archives of Thermodynamics

Rocznik

2011

Numer

No 4 December

Autorzy publikacji

Wydział PAN

Nauki Techniczne

Wydawca

The Committee on Thermodynamics and Combustion of the Polish Academy of Sciences

Data

2011

Identyfikator

ISSN 1231-0956 ; eISSN 2083-6023

Referencje

Preusser G. (1996), Concept for the analysis of hydrogen problems in nuclear power plants after accidents, null, 113. ; OECD/NEA: <i>SOAR on containment thermalhydraulics and hydrogen distribution.</i> Report NEA/CSNI(R)99/16. Paris 1999. ; De Boeck B.: <i>Introduction to severe accidents. Especially the containment behaviour.</i> AIB VINCOTTE NUCLEAR report AVN 97/013. See also: <a target="_blank" href='http://www.avn.org'>http://www.avn.org</a> ; OECD/NEA: <i>PWR fuel behaviour in design basis accident conditions.</i> Report CSNI86/129, Paris 1986. ; OECD/NEA: <i>Source term assessment, containment atmosphere control systems and accident consequences.</i> Report CSNI87/135, Paris 1987. ; Fic A. (1993), Mathematical model of transient thermal and flow processes in containment of a PWR nuclear reactor, Archiwum Energetyki, XXXII, 1-2, 19. ; Skorek J. (1994), 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, 217. ; Bury T.: <i>Analysis of thermal and flow processes within containments of water nuclear reactors during loss-of-coolant accidents.</i> PhD thesis, Institute of Thermal Technology, Silesian University of Technology, Gliwice 2005. ; <i>Micro-Simulation Technology. PCTRAN/PWR - Personal Computer Transient Analyzer for a Two-loop PWR.</i> Micro-Simulation Technology, Montville, New Jersey, 2004. ; Florida Power&Light Company: <i>Final safety analysis report for Turkey Point unit 3 and 4.</i> Biscayne Bay, Florida, 1997. ; Bury T. (2004), Prediction of hydrogen concentration during LOCA within the VVER 440/213 containment, null. ; Deng J. (2008), A study on evaluating a passive autocatalytic recombiner PAR-system in the PWR large-dry containment, Nuclear Engineering and Design, 238, 2554, doi.org/10.1016/j.nucengdes.2008.04.011

DOI

10.2478/v10173-011-0032-2

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