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Proceedings Papers

Cyber Resilience Analysis of SCADA Systems in Nuclear Power Plants

Meghan Galiardi, Amanda Gonzales, Jamie Thorpe, Eric Vugrin, Raymond Fasano, Christopher Lamb
Proc. ASME. ICONE2020, Volume 2: Nuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors, V002T08A003, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16071
https://doi.org/10.1115/ICONE2020-16071
View Paper titled, Cyber Resilience Analysis of SCADA Systems in Nuclear Power Plants
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Topics: Nuclear power stations, Resilience, Supervisory Control and Data Acquisition systems, Control systems, Architecture, Design, Security, Computer security, Computer software, Hardware
Proceedings Papers

Expected Accuracy Range of Cost Estimates for Small Modular Reactors at the Early Concept Design Stage

Amritpal S. Agar, Andy J. Fry, Martin J. Goodfellow, Yee M. Goh, Linda B. Newnes
Proc. ASME. ICONE26, Volume 9: Student Paper Competition, V009T16A055, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81799
https://doi.org/10.1115/ICONE26-81799
View Paper titled, Expected Accuracy Range of Cost Estimates for Small Modular Reactors at the Early Concept Design Stage
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Topics: Design, Project cost estimation, Small modular reactors, Life cycle costing, Nuclear power stations, Uncertainty, Certainty, Energy generation, Risk, Construction
Proceedings Papers

Learning Through Delivery, Westinghouse AP1000® Plant Licensing

Julie Gorgemans, Michael M. Corletti, Richard A. DeLong, Terry L. Schulz
Proc. ASME. ICONE22, Volume 1: Plant Operations, Maintenance, Engineering, Modifications, Life Cycle and Balance of Plant; Nuclear Fuel and Materials; Plant Systems, Structures and Components; Codes, Standards, Licensing and Regulatory Issues, V001T07A019, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-31204
https://doi.org/10.1115/ICONE22-31204
View Paper titled, Learning Through Delivery, Westinghouse AP1000® Plant Licensing
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Topics: Licensing, Construction, China, Design, Plant design, Pressurized water reactors, Safety, Certainty, Maintenance, Shorelines
Proceedings Papers

CANDU Position and Prospect in Chinese Nuclear Fuel Cycle

Zhenhua Zhang, Mingjun Chen, Peide Zhou, Qing Li, Zhiliang Meng, Guowei Zhang
Proc. ASME. ICONE21, Volume 1: Plant Operations, Maintenance, Engineering, Modifications, Life Cycle and Balance of Plant; Nuclear Fuel and Materials; Radiation Protection and Nuclear Technology Applications, V001T02A046, July 29–August 2, 2013
Publisher: American Society of Mechanical Engineers
Paper No: ICONE21-16727
https://doi.org/10.1115/ICONE21-16727
View Paper titled, CANDU Position and Prospect in Chinese Nuclear Fuel Cycle
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Topics: Nuclear fuel cycle, Nuclear power, Uranium, Certainty, China, Climate, Recycling, Sustainable development, Thermal reactors
Proceedings Papers

R&D of Validity Evaluation System for Seismic Simulation of Entire Nuclear Plant

Yoshio Suzuki, Hiroko Nakamura Miyamura, Norihiro Nakajima
Proc. ASME. ICONE20-POWER2012, Volume 2: Plant Systems, Structures, and Components; Safety and Security; Next Generation Systems; Heat Exchangers and Cooling Systems, 43-51, July 30–August 3, 2012
Publisher: American Society of Mechanical Engineers
Paper No: ICONE20-POWER2012-54231
https://doi.org/10.1115/ICONE20-POWER2012-54231
View Paper titled, R&D of Validity Evaluation System for Seismic Simulation of Entire Nuclear Plant
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Topics: Nuclear power stations, Simulation, Uncertainty, Certainty, Computer simulation, Simulation results, Chaos, Manufacturing, Safety, Security
Proceedings Papers

International Training Program in Support of Safety Analysis: 3D S.UN.COP — S caling, Un certainty and 3D Thermalhydraulics/Neutron-Kinetics Co u p led Codes Seminar

A. Petruzzi, F. Fiori, A. Kovtonyuk, F. D’Auria, T. Bajs, F. Reventos
Proc. ASME. ICONE20-POWER2012, Volume 1: Plant Operations, Maintenance, Engineering, Modifications, Life Cycle, and Balance of Plant; Component Reliability and Materials Issues; Steam Generator Technology Applications and Innovations; Advanced Reactors and Near-Term Deployment; Reactor Physics, Neutronics, and Transport Theory; Nuclear Education, Human Resources, and Public Acceptance, 861-871, July 30–August 3, 2012
Publisher: American Society of Mechanical Engineers
Paper No: ICONE20-POWER2012-55230
https://doi.org/10.1115/ICONE20-POWER2012-55230
View Paper titled, International Training Program in Support of Safety Analysis: 3D S.UN.COP — S caling, Un certainty and 3D Thermalhydraulics/Neutron-Kinetics Co u p led Codes Seminar
Open the PDF for International Training Program in Support of Safety Analysis: 3D S.UN.COP — S caling, Un certainty and 3D Thermalhydraulics/Neutron-Kinetics Co u p led Codes Seminar in another window
Topics: Certainty, Neutrons, Safety, Training programs, Computers, Nuclear power, Nuclear power stations, Uncertainty, Education, Engineering teachers
Proceedings Papers

Study on the Predicting Model of Onset of Nucleate Boiling in Natural Circulation Based on Unascertained Mathematics

Ming Zhang, Tao Zhou, Ping Liu, Ke Ran, Cheng Sheng, Tao Fu, Zejun Xiao
Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 4, Parts A and B, 465-470, May 17–21, 2010
Publisher: American Society of Mechanical Engineers
Paper No: ICONE18-29419
https://doi.org/10.1115/ICONE18-29419
View Paper titled, Study on the Predicting Model of Onset of Nucleate Boiling in Natural Circulation Based on Unascertained Mathematics
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Topics: Mathematics, Nucleate boiling, Boiling, Heat transfer, Subcooling, Certainty, Circuits, Flow (Dynamics), Nuclear power stations, Pressurized water reactors
Proceedings Papers

Study on Applicability of Simple Conversion Factor for In-Situ Activity Measurement

Yuko Onishi, Satoru Kawasaki, Masami Kato
Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 1, 571-575, May 17–21, 2010
Publisher: American Society of Mechanical Engineers
Paper No: ICONE18-30166
https://doi.org/10.1115/ICONE18-30166
View Paper titled, Study on Applicability of Simple Conversion Factor for In-Situ Activity Measurement
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Topics: Calibration, Certainty, Clearances (Engineering), Computer software, Concretes, Density, Metals, Nuclear power stations, Radiation sources, Radioisotopes
Proceedings Papers

International Training Program in Support of Safety Analysis: 3D S.UN.COP— S caling, Un certainty and 3D Thermal-Hydraulics/Neutron-Kinetics Co u p led Codes Seminars

Alessandro Petruzzi, Francesco D’Auria, Tomislav Bajs, Francesc Reventos
Proc. ASME. ICONE17, Volume 3: Thermal Hydraulics; Current Advanced Reactors: Plant Design, Construction, Workforce and Public Acceptance, 843-852, July 12–16, 2009
Publisher: American Society of Mechanical Engineers
Paper No: ICONE17-76056
https://doi.org/10.1115/ICONE17-76056
View Paper titled, International Training Program in Support of Safety Analysis: 3D S.UN.COP— S caling, Un certainty and 3D Thermal-Hydraulics/Neutron-Kinetics Co u p led Codes Seminars
Open the PDF for International Training Program in Support of Safety Analysis: 3D S.UN.COP— S caling, Un certainty and 3D Thermal-Hydraulics/Neutron-Kinetics Co u p led Codes Seminars in another window
Topics: Certainty, Neutrons, Safety, Thermal hydraulics, Training programs, Uncertainty, Computers, Nuclear power stations, Education, Industrial engineering
Proceedings Papers

International Training Program in Support of Safety Analysis: 3D S.UN.COP— S caling, Un certainty and 3D Thermal-Hydraulics/Neutron-Kinetics Co u p led Codes Seminars

Alessandro Petruzzi, Francesco D’Auria, Tomislav Bajs, Francesc Reventos
Proc. ASME. ICONE14, Volume 5: Safety and Security; Low Level Waste Management, Decontamination and Decommissioning; Nuclear Industry Forum, 433-442, July 17–20, 2006
Publisher: American Society of Mechanical Engineers
Paper No: ICONE14-89902
https://doi.org/10.1115/ICONE14-89902
View Paper titled, International Training Program in Support of Safety Analysis: 3D S.UN.COP— S caling, Un certainty and 3D Thermal-Hydraulics/Neutron-Kinetics Co u p led Codes Seminars
Open the PDF for International Training Program in Support of Safety Analysis: 3D S.UN.COP— S caling, Un certainty and 3D Thermal-Hydraulics/Neutron-Kinetics Co u p led Codes Seminars in another window
Topics: Certainty, Computers, Education, Engineering teachers, Industrial engineering, Neutrons, Nuclear fuels, Nuclear power stations, Public utilities, Safety
Proceedings Papers

Power Recapture and Power Uprate in NPPs With Process Data Reconciliation in Accordance With VDI 2048

Magnus Langenstein
Proc. ASME. ICONE14, Volume 1: Plant Operations, Maintenance and Life Cycle; Component Reliability and Materials Issues; Codes, Standards, Licensing and Regulatory Issues; Fuel Cycle and High Level Waste Management, 7-14, July 17–20, 2006
Publisher: American Society of Mechanical Engineers
Paper No: ICONE14-89025
https://doi.org/10.1115/ICONE14-89025
View Paper titled, Power Recapture and Power Uprate in NPPs With Process Data Reconciliation in Accordance With VDI 2048
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Topics: Boilers, Boiling water reactors, Calibration, Certainty, Design, Emergencies, Errors, Heat, Instrumentation, Nuclear power stations