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Guido Mazzini
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Journal Articles

Hydrogen Deflagration Analysis in THAI Experiments Using MELCOR Code

Alain Flores y Flores, Guido Mazzini
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2022, 8(3): 031201.
Paper No: NERS-20-1034
https://doi.org/10.1115/1.4048006
Published Online: May 27, 2022
View Article titled, Hydrogen Deflagration Analysis in THAI Experiments Using MELCOR Code
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Topics: Explosions, Hydrogen, Aerosols, Thermal hydraulics, Pressure, Flames, Test facilities
Journal Articles

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

Guido Mazzini, Alis Musa, Rostilav Fukac
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2021, 7(2): 021404.
Paper No: NERS-20-1157
https://doi.org/10.1115/1.4050207
Published Online: March 10, 2021
View Article titled, Simulation of the Super Critical Water Loop Using ATHLET Code During an Abnormal Scenario
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Topics: Flow (Dynamics), Pressure, Safety, Simulation, Temperature, Transients (Dynamics), Water, Heat transfer, Pumps, Light water reactors
Journal Articles

Energy Well: Concept of 20 MW Microreactor Cooled by Molten Salts

Marek Ruščák, Tomáš Melichar, Jan Syblík, Otakar Frýbort, David Harut, Evžen Losa, Martin Mareček, Guido Mazzini, Mathieu Reungoat, Jan Pilát, Marek Benčik, Pavel Král
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2021, 7(2): 021302.
Paper No: NERS-20-1077
https://doi.org/10.1115/1.4049715
Published Online: February 19, 2021
View Article titled, Energy Well: Concept of 20 MW Microreactor Cooled by Molten Salts
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Topics: Circuits, Heat, Cooling, Fuels, Safety
Journal Articles

Estimation of Tritium and Dust Source Term in European DEMOnstration Fusion Reactor During Accident Scenarios

Guido Mazzini, Tadas Kaliatka, Maria Teresa Porfiri
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2019, 5(3): 030916.
Paper No: NERS-18-1100
https://doi.org/10.1115/1.4043379
Published Online: May 29, 2019
View Article titled, Estimation of Tritium and Dust Source Term in European DEMOnstration Fusion Reactor During Accident Scenarios
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Topics: Accidents, Dust, Plasmas (Ionized gases), Fusion reactors, Safety, Vessels
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
View Article titled, Assessment of the TRACE 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
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
Proceedings Papers

Neutronic Analysis for VVER-440 Type Reactor Using PARCS Code

Luca Ratti, Guido Mazzini, Marek Ruščák, Valerio Giusti
Proc. ASME. ICONE26, Volume 9: Student Paper Competition, V009T16A096, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-82607
https://doi.org/10.1115/ICONE26-82607
View Paper titled, Neutronic Analysis for VVER-440 Type Reactor Using PARCS Code
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Topics: Accidents, Cross section (Physics), Design, Fuels, Nuclear power stations, Radiation (Physics), Safety
Journal Articles

Analyses of Feedwater Trip With SBO Sequence of VVER1000 Reactor

Guido Mazzini, Miloš Kynčl, Marek Ruščák
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Technical Briefs
ASME J of Nuclear Rad Sci. October 2016, 2(4): 044505.
Paper No: NERS-15-1221
https://doi.org/10.1115/1.4034144
Published Online: October 12, 2016
View Article titled, Analyses of Feedwater Trip With SBO Sequence of VVER1000 Reactor
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Topics: Accidents, Design, Feedwater, Flow (Dynamics), Fukushima nuclear disaster, Japan, 2011, Hydrogen production, Leakage, Nuclear engineering, Nuclear power stations, Pressure
Journal Articles

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

Davide Chersola, Guglielmo Lomonaco, Guido Mazzini
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research Papers
ASME J of Nuclear Rad Sci. July 2015, 1(3): 031004.
Paper No: NERS-14-1027
https://doi.org/10.1115/1.4029521
Published Online: May 20, 2015
View Article titled, Cross-Section Influence on Monte Carlo-Based Burn-Up Codes Applied to a GFR-Like Configuration
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Topics: Cross section (Physics), Density, Flux (Metallurgy), Fuels, Nuclides, Spectra (Spectroscopy), Nuclear fission, Fast neutron reactors
Proceedings Papers

Analyses of the Start-Up and Shut-Down of SCWR Fuel Qualification Test Loop

Ales Vojacek, Guido Mazzini
Proc. ASME. ICONE22, Volume 2B: Thermal Hydraulics, V02BT09A012, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-30673
https://doi.org/10.1115/ICONE22-30673
View Paper titled, Analyses of the Start-Up and Shut-Down of SCWR Fuel Qualification Test Loop
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Topics: Fuels, Supercritical water reactors, Manufacturing, Circuits, Cooling, Design, Engineering simulation, Heat transfer, Heating, Licensing
Proceedings Papers

Comparison Between PARCS and MCNP6 Codes on VVER1000/V320 Core

Guido Mazzini, Bruno Miglierini, Marek Ruščák
Proc. ASME. ICONE22, Volume 4: Radiation Protection and Nuclear Technology Applications; Fuel Cycle, Radioactive Waste Management and Decommissioning; Computational Fluid Dynamics (CFD) and Coupled Codes; Reactor Physics and Transport Theory, V004T11A007, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-30386
https://doi.org/10.1115/ICONE22-30386
View Paper titled, Comparison Between PARCS and MCNP6 Codes on VVER1000/V320 Core
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Topics: Accidents, Boron, Cross section (Physics), Design, Engineering simulation, Neutrons, Nuclear power stations, Nuclear reactor kinetics, Pressurized water reactors, Safety
Proceedings Papers

Cross Sections Influence on Monte Carlo Based Burnup Codes

Davide Chersola, Guglielmo Lomonaco, Guido Mazzini
Proc. ASME. ICONE22, Volume 4: Radiation Protection and Nuclear Technology Applications; Fuel Cycle, Radioactive Waste Management and Decommissioning; Computational Fluid Dynamics (CFD) and Coupled Codes; Reactor Physics and Transport Theory, V004T11A015, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-31049
https://doi.org/10.1115/ICONE22-31049
View Paper titled, Cross Sections Influence on Monte Carlo Based Burnup Codes
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Topics: Cross section (Physics), Flux (Metallurgy), Nuclides