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RISVVER 1000 Severe Accident Analyses Using MELCOR Code
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 ...
Assessment of the TRACE Code for the He-Cooled Systems Simulation Capability Against Some He-FUS3 Experimental Measurements
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 ...