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    VVER 1000 Severe Accident Analyses Using MELCOR Code 

    Source: Journal of Nuclear Engineering and Radiation Science:;2019:;volume( 005 ):;issue: 003:;page 30913
    Author(s): Ruščák, Marek; Mazzini, Guido; Kynčl, Milos; Savanyuk, Sevastyan; Hrehor, Miroslav; Musa, Alis; Flores y Flores, Alain
    Publisher: American Society of Mechanical Engineers (ASME)
    Abstract: This work describes the computer model development of the water–water energetic reactor (VVER) 1000 nuclear power plant (NPP) in the methods for estimation of leakages and consequences of releases (MELCOR) 1.8.6 code and ...
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