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Proceedings Papers

Codes and Methods Improvements for VVER Comprehensive Safety Assessment: The CAMIVVER H2020 Project

Denis Verrier, Barbara Vezzoni, Barbara Calgaro, Olivier Bernard, Alberto Previti, Clément Lafaurie, Artur Hashymov, Pavlin Groudev, Antoaneta Stefanova, Neli Zaharieva, Frédéric Damian, Pietro Mosca, Daniele Tomatis, Ulrich Bieder, Adrien Willien, Nicolas Dos Santos, Luigi Mercatali, Victor Hugo Sanchez-Espinoza, Nicola Forgione, Sandro Paci
Proc. ASME. ICONE28, Volume 2: Nuclear Fuels, Research, and Fuel Cycle; Nuclear Codes and Standards; Thermal-Hydraulics, V002T07A010, August 4–6, 2021
Paper No: ICONE28-64169
DOI: https://doi.org/10.1115/ICONE28-64169
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Topics: Physics, Pressurized water reactors, Safety, Computers, Computational fluid dynamics, Maintenance, Modeling, Nuclear industry, Security, Thermal hydraulics
Proceedings Papers

Stand-Alone Containment Analysis of the Phébus FPT-3 Test With the ASTEC and the MELCOR Codes

Bruno Gonfiotti, Sandro Paci
Proc. ASME. ICONE26, Volume 4: Nuclear Safety, Security, and Cyber Security; Computer Code Verification and Validation, V004T15A002, July 22–26, 2018
Paper No: ICONE26-81139
DOI: https://doi.org/10.1115/ICONE26-81139
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Topics: Containment, Accidents, Aerosols, Sensitivity analysis, Computer simulation, Fuels, Pressurized water reactors, Safety, Thermal hydraulics, Transients (Dynamics)
Journal Articles

Stand-Alone Containment Analysis of the Phébus Fission Products Test 1 With the ASTEC and the MELCOR Codes

Bruno Gonfiotti, Sandro Paci
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2018, 4(2): 020902.
Paper No: NERS-16-1115
DOI: https://doi.org/10.1115/1.4038059
Published Online: March 5, 2018
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Topics: Aerosols, Containment, Nuclear fission, Temperature, Sensitivity analysis, Water, Condensers (steam plant), Thermal hydraulics, Condensation
Proceedings Papers

Stand-Alone Containment Analysis of the PHÉBUS FPT-1 Test With the ASTEC and the MELCOR Codes

Bruno Gonfiotti, Sandro Paci
Proc. ASME. ICONE24, Volume 4: Computational Fluid Dynamics (CFD) and Coupled Codes; Decontamination and Decommissioning, Radiation Protection, Shielding, and Waste Management; Workforce Development, Nuclear Education and Public Acceptance; Mitigation Strategies for Beyond Design Basis Events; Risk Management, V004T13A005, June 26–30, 2016
Paper No: ICONE24-60184
DOI: https://doi.org/10.1115/ICONE24-60184
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Topics: Containment, Accidents, Aerosols, Containment systems, Containment vessels, Coolants, Nuclear fission, Nuclear power stations, Sensitivity analysis, Thermal hydraulics
Proceedings Papers

Validation of a CFD Condensation Model Based on Heat and Mass Transfer Analogy by TOSQAN Facility ISP47 Test

Matteo Bucci, Walter Ambrosini, Nicola Forgione, Francesco Oriolo, Sandro Paci
Proc. ASME. ICONE14, Volume 4: Computational Fluid Dynamics, Neutronics Methods and Coupled Codes; Student Paper Competition, 479-486, July 17–20, 2006
Paper No: ICONE14-89101
DOI: https://doi.org/10.1115/ICONE14-89101
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Topics: Computational fluid dynamics, Condensation, Heat, Mass transfer, Vessels, Containment, Design, Engineering standards, Momentum, Nuclear reactors