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    Simulation of the Super Critical Water Loop Using ATHLET Code During an Abnormal Scenario 

    Source: Journal of Nuclear Engineering and Radiation Science:;2021:;volume( 007 ):;issue: 002:;page 021404-1
    Author(s): Mazzini, Guido; Musa, Alis; Fukac, Rostilav
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: Supercritical water (SCW) has advantages like high thermal efficiency and can operate at high temperature and pressure. At the same time, however, these properties bring up related issues, such as material compatibility ...
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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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    Assessment of the TRACE Code for the He-Cooled Systems Simulation Capability Against Some He-FUS3 Experimental Measurements 

    Source: Journal of Nuclear Engineering and Radiation Science:;2019:;volume( 005 ):;issue: 003:;page 30914
    Author(s): Mazzini, Guido; Kynčl, Miloš; Ruščák, Marek; Hrehor, Miroslav; Musa, Alis; Dambrosio, Antonio; Romanello, Vincenzo
    Publisher: American Society of Mechanical Engineers (ASME)
    Abstract: This paper focuses on the TRACE code assessment for helium-cooled systems thermal-hydraulic analysis. In the frame of the GoFastR (gas cooled fast reactor) European Collaborative Project, ENEA has offered some selected ...
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