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Proc. ASME. ICONE2020, Volume 1: Beyond Design Basis; Codes and Standards; Computational Fluid Dynamics (CFD); Decontamination and Decommissioning; Nuclear Fuel and Engineering; Nuclear Plant Engineering, V001T01A016, August 4–5, 2020

Paper No: ICONE2020-16664

DOI: https://doi.org/10.1115/ICONE2020-16664

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Topics: Failure, Finite element methods, Pressurized water reactors, Accidents, Nuclear power stations, Reactor vessels, Boundary-value problems, Computers, Engineering simulation, Materials properties

Proceedings Papers

Large-Scale Rig for the Characterization of DCC at Sub-Atmospheric Pressure

R. Lo Frano, A. Pesetti, D. Aquaro, M. Olcese

Proc. ASME. ICONE2020, Volume 2: Nuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors, V002T11A012, August 4–5, 2020

Paper No: ICONE2020-16662

DOI: https://doi.org/10.1115/ICONE2020-16662

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Topics: Condensation, Pressure, Safety

Proceedings Papers

Feasibility Study of a New Fabrication Method for the Li4SiO4 Pebbles

R. Lo Frano, M. Puccini, E. Stefanelli

Paper No: ICONE2020-16711

DOI: https://doi.org/10.1115/ICONE2020-16711

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Topics: Manufacturing

Proceedings Papers

Feasibility Study of a New Fabrication Method for the Li4SiO4 Pebbles

R. Lo Frano, M. Puccini, E. Stefanelli, M. Luppichini, C. Grima, S. Vitolo, D. Aquaro, S. Malquori, S. De Sanctis

Proc. ASME. ICONE26, Volume 5: Advanced Reactors and Fusion Technologies; Codes, Standards, Licensing, and Regulatory Issues, V005T05A030, July 22–26, 2018

Paper No: ICONE26-82598

DOI: https://doi.org/10.1115/ICONE26-82598

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Topics: Manufacturing, Casting, Collaboration, Graphite, High temperature, Lithium, Microfluidics, Sprays, Temperature

Proceedings Papers

Analysis of Vibrations due to the Steam Condensation at Sub-Atmospheric Condition

G. Giambartolomei, R. Lo Frano, D. Mazed, D. Del Serra, D. Aquaro

Proc. ASME. ICONE26, Volume 5: Advanced Reactors and Fusion Technologies; Codes, Standards, Licensing, and Regulatory Issues, V005T05A026, July 22–26, 2018

Paper No: ICONE26-82378

DOI: https://doi.org/10.1115/ICONE26-82378

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Topics: Condensation, Steam, Vibration, Oscillations, Flow (Dynamics), Pressure, Water, Boiling water reactors, Cooling systems, Damage

Proceedings Papers

Methodology to Investigate Vibration Phenomena Caused by the Steam Condensation at Subatmospheric Condition

R. Lo Frano, D. Mazed, D. Aquaro, D. Del Serra, I. Sekachev, G. Giambartolomei

Proc. ASME. ICONE25, Volume 5: Advanced and Next Generation Reactors, Fusion Technology; Codes, Standards, Conformity Assessment, Licensing, and Regulatory Issues, V005T05A042, July 2–6, 2017

Paper No: ICONE25-67448

DOI: https://doi.org/10.1115/ICONE25-67448

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Topics: Condensation, Steam, Vibration, Water, Oscillations, Safety, Accidents, Boiling water reactors, Finite element methods, Finite element model

Proceedings Papers

Preliminary Safety Evaluation of an Aircraft Impact on a Near-Surface Radioactive Waste Repository

R. Lo Frano, G. Forasassi, G. Pugliese

Proc. ASME. ICEM2013, Volume 1: Low/Intermediate-Level Radioactive Waste Management; Spent Fuel, Fissile Material, Transuranic and High-Level Radioactive Waste Management, V001T01A042, September 8–12, 2013

Paper No: ICEM2013-96235

DOI: https://doi.org/10.1115/ICEM2013-96235

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Topics: Aircraft, Radioactive waste repositories, Safety, Design, Stress, Military systems, Accidents, Computer simulation, Concrete walls, Concretes

Proceedings Papers

Application of PHADEC Method for the Decontamination of Radioactive Steam Piping Components

R. Lo Frano, F. Pilo, D. Aquaro

Proc. ASME. ICEM2013, Volume 2: Facility Decontamination and Decommissioning; Environmental Remediation; Environmental Management/Public Involvement/Crosscutting Issues/Global Partnering, V002T03A038, September 8–12, 2013

Paper No: ICEM2013-96252

DOI: https://doi.org/10.1115/ICEM2013-96252

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Topics: Decontamination, Pipes, Steam, Iron, Nuclear power stations, Radioactivity, Clearances (Engineering), Contamination, Geometry, High pressure (Physics)

Proceedings Papers

Evaluation of the Isolation System Influence in the Seismic Loading Analysis Applied to a Near Term Deployment Reactor

R. Lo Frano, G. Forasassi

Proc. ASME. ICONE17, Volume 2: Structural Integrity; Safety and Security; Advanced Applications of Nuclear Technology; Balance of Plant for Nuclear Applications, 143-151, July 12–16, 2009

Paper No: ICONE17-75459

DOI: https://doi.org/10.1115/ICONE17-75459

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Topics: Dampers, Design, Earthquake risk, Earthquakes, Energy dissipation, Finite element analysis, Nuclear power stations, Nuclear reactors, Safety, Seismic analysis

Proceedings Papers

Seismic Analysis Approach Applied to a Small Size Next Generation Nuclear Reactor

G. Forasassi, R. Lo Frano

Proc. ASME. ICONE16, Volume 4: Structural Integrity; Next Generation Systems; Safety and Security; Low Level Waste Management and Decommissioning; Near Term Deployment: Plant Designs, Licensing, Construction, Workforce and Public Acceptance, 45-53, May 11–15, 2008

Paper No: ICONE16-48146

DOI: https://doi.org/10.1115/ICONE16-48146

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Topics: Nuclear power stations, Nuclear reactors, Seismic analysis, Safety, Earthquakes, Geometry, Stress, Bearings, Design, Dynamic response

Proceedings Papers

Seismic Response of Reactor Vessel Internals in the IRIS Reactor

D. Aquaro, M. D. Carelli, G. Forasassi, R. Lo Frano, N. Zaccari

Proc. ASME. ICONE14, Volume 3: Structural Integrity; Nuclear Engineering Advances; Next Generation Systems; Near Term Deployment and Promotion of Nuclear Energy, 229-238, July 17–20, 2006

Paper No: ICONE14-89579

DOI: https://doi.org/10.1115/ICONE14-89579

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Topics: Computer simulation, Containment systems, Design, Finite element methods, Nuclear power stations, Nuclear reactors, Optimization, Pressurized water reactors, Reactor vessels, Seismic analysis

Journal citation

NARROW

Inverse Heat Conduction Problem in Estimating Nuclear Power Plant Piping Performance

Pipe Performance in Long Term Operation Framework: Ageing Issues

Study of the Ageing Effects on the Lower Head Failure in a PWR Reactor

Large-Scale Rig for the Characterization of DCC at Sub-Atmospheric Pressure

Feasibility Study of a New Fabrication Method for the Li4SiO4 Pebbles

Feasibility Study of a New Fabrication Method for the Li4SiO4 Pebbles

Analysis of Vibrations due to the Steam Condensation at Sub-Atmospheric Condition

Methodology to Investigate Vibration Phenomena Caused by the Steam Condensation at Subatmospheric Condition

Preliminary Safety Evaluation of an Aircraft Impact on a Near-Surface Radioactive Waste Repository

Application of PHADEC Method for the Decontamination of Radioactive Steam Piping Components

Evaluation of the Isolation System Influence in the Seismic Loading Analysis Applied to a Near Term Deployment Reactor

Seismic Analysis Approach Applied to a Small Size Next Generation Nuclear Reactor

Seismic Response of Reactor Vessel Internals in the IRIS Reactor

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