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Journal Articles

Methodology for Calculating Minor Radioactive Releases From VVER 1000 Using TRACE Code

M. Ruscak, G. Mazzini, A. Dambrosio, A. Musa
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2021, 7(2): 021402.
Paper No: NERS-20-1208
https://doi.org/10.1115/1.4049854
Published Online: February 26, 2021
... of a real operational incident scenario using a standard thermal hydraulic model of the power plant in the TRACE code that was originally intended for simulation of design basis accidents such as large break coolant accident or loss of flow accident. Special attention was given to the methodology...
View Article titled, Methodology for Calculating Minor Radioactive Releases From VVER 1000 Using <span class="search-highlight">TRACE</span> Code
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Topics: Accidents, Coolants, Flow (Dynamics), Pressure, Safety, Simulation, Water, Nuclear power stations, Feedwater, Design
Journal Articles

Assessment of the TRACE Code for the He-Cooled Systems Simulation Capability Against Some He-FUS3 Experimental Measurements

Guido Mazzini, Miloš Kynčl, Marek Ruščák, Miroslav Hrehor, Alis Musa, Antonio Dambrosio, Vincenzo Romanello
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2019, 5(3): 030914.
Paper No: NERS-18-1085
https://doi.org/10.1115/1.4043377
Published Online: May 10, 2019
...Guido Mazzini; Miloš Kynčl; Marek Ruščák; Miroslav Hrehor; Alis Musa; Antonio Dambrosio; Vincenzo Romanello 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...
View Article titled, Assessment of the <span class="search-highlight">TRACE</span> Code for the He-Cooled Systems Simulation Capability Against Some He-FUS3 Experimental Measurements
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Topics: Helium, Simulation, Steady state, Temperature, Flow (Dynamics), Compressors, Coolants, Pipes
Journal Articles

VVER 1000 Severe Accident Analyses Using MELCOR Code

Marek Ruščák, Guido Mazzini, Milos Kynčl, Sevastyan Savanyuk, Miroslav Hrehor, Alis Musa, Alain Flores y Flores
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2019, 5(3): 030913.
Paper No: NERS-18-1086
https://doi.org/10.1115/1.4043378
Published Online: April 19, 2019
... and steam pressure. The VVER 1000 reactor nodalization in the MELCOR code is based on the TRACE power plant model with respect to the differences of the input data sets for both codes [ 4 ]. Defining the input deck, the heat structures and the control volumes, was prepared by a standard methodology...
View Article titled, VVER 1000 Severe Accident Analyses Using MELCOR Code
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Topics: Accidents, Containment, Pressure, Water, Temperature, Nuclear fission, Failure, Leakage, Boilers