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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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    Cross Section Influence on Monte Carlo Based Burn Up Codes Applied to a GFR Like Configuration 

    Source: Journal of Nuclear Engineering and Radiation Science:;2015:;volume( 001 ):;issue: 003:;page 31004
    Author(s): Chersola, Davide; Lomonaco, Guglielmo; Mazzini, Guido
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: This paper reports the results of a comparison among JEFF and ENDF/B data sets when used by SERPENT and MONTEBURNS codes on a gascooled fast reactor (GFR)like configuration. Particularly, it shows a comparison between the ...
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    Analyses of Feedwater Trip With SBO Sequence of VVER1000 Reactor 

    Source: Journal of Nuclear Engineering and Radiation Science:;2016:;volume( 002 ):;issue: 004:;page 44505
    Author(s): Mazzini, Guido; Kynčl, Miloš; Ruščák, Marek
    Publisher: The American Society of Mechanical Engineers (ASME)
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    Estimation of Tritium and Dust Source Term in European DEMOnstration Fusion Reactor During Accident Scenarios 

    Source: Journal of Nuclear Engineering and Radiation Science:;2019:;volume( 005 ):;issue: 003:;page 30916
    Author(s): Mazzini, Guido; Kaliatka, Tadas; Porfiri, Maria Teresa
    Publisher: American Society of Mechanical Engineers (ASME)
    Abstract: The safety features of the future nuclear fusion reactors are one of the key issues for their attractiveness if compared with the fission plants. In fusion devices, accidents with high release of radioactive materials have ...
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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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    Energy Well: Concept of 20 MW Microreactor Cooled by Molten Salts 

    Source: Journal of Nuclear Engineering and Radiation Science:;2021:;volume( 007 ):;issue: 002:;page 021302-1
    Author(s): Ruščák, Marek; Melichar, Tomáš; Syblík, Jan; Frýbort, Otakar; Harut, David; Losa, Evžen; Mareček, Martin; Mazzini, Guido; Reungoat, Mathieu; Pilát, Jan; Benčik, Marek; Král, Pavel
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: In this paper is described the concept of a 20 MW microreactor cooled by molten salts with the registered trademark of Energy Well. Energy Well reactor is designed to supply either electricity or heat, in remote areas or ...
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