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Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A095, August 8–12, 2022

Paper No: ICONE29-94480

DOI: https://doi.org/10.1115/ICONE29-94480

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Topics: Machine learning, Boron, Corrosion, Fuels, Nuclear power stations, Algorithms, Calibration, Chemistry, Cladding systems (Building), Computers

Proceedings Papers

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

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

Equal Forced Time Step Approach to PSA for a Dynamic System – A Case of the Holdup Tank

E. E. Taapopi, H. Wang, J. Zhou

Proc. ASME. ICONE28, Volume 3: Computational Fluid Dynamics (CFD); Verification and Validation; Advanced Methods of Manufacturing (AMM) for Nuclear Reactors and Components; Decontamination, Decommissioning, and Radioactive Waste Management; Beyond Design Basis and Nuclear Safety; Risk Informed Management and Regulation, V003T12A011, August 4–6, 2021

Paper No: ICONE28-64081

DOI: https://doi.org/10.1115/ICONE28-64081

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Topics: Accidents, Boilers, Computers, Dynamic systems, Errors, Failure, Failure mechanisms, Nuclear power stations, Pressure, Probability

Proceedings Papers

RELAP5-3D Sensitivity Studies of Incorporating Axial Boron Gradients Into a Heater Tube Experiment for Pool Boiling CHF Testing in TREAT

Richard Hernandez, Nicholas R. Brown, Charles P. Folsom, Nicolas E. Woolstenhulme, Colby B. Jensen

Proc. ASME. ICONE2020, Volume 3: Student Paper Competition; Thermal-Hydraulics; Verification and Validation, V003T13A041, August 4–5, 2020

Paper No: ICONE2020-16758

DOI: https://doi.org/10.1115/ICONE2020-16758

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Topics: Boron, Critical heat flux, Pool boiling, Testing, Coolants, Design, Shapes, Accidents, Heat flux, Heat transfer

Proceedings Papers

Simulation of Severe Accident Progression Using ROSHNI: A New Integrated Simulation Code for PHWR Severe Accidents

Sunil Nijhawan, YongMann Song

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, V001T01A014, August 4–5, 2020

Paper No: ICONE2020-16633

DOI: https://doi.org/10.1115/ICONE2020-16633

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Topics: Accidents, Heavy water reactors, Simulation, Fuels, Design, Modeling, Vessels, Damage, Failure, Fluids

Proceedings Papers

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

R. Lo Frano, S. Paci, P. Darnowski, P. Mazgaj

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

Research of Fast Modeling and Simulating Platform for Nuclear Power Plant Secondary Loop

Meijie Gong, Minjun Peng, Haishan Zhu

Proc. ASME. ICONE26, Volume 9: Student Paper Competition, V009T16A053, July 22–26, 2018

Paper No: ICONE26-81779

DOI: https://doi.org/10.1115/ICONE26-81779

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Topics: Modeling, Nuclear power stations, Simulation, Simulation models, Computers, Design, Simulation results

Proceedings Papers

Dose Minimization Game for Smartphones

Nolan Stelter, Arnav Das, Zahra Hanifah, Rizwan Uddin

Proc. ASME. ICONE26, Volume 9: Student Paper Competition, V009T16A089, July 22–26, 2018

Paper No: ICONE26-82450

DOI: https://doi.org/10.1115/ICONE26-82450

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Topics: Computers, Education, Modeling, Nuclear power, Physics, Radiation (Physics), Radiation sources, Teaching, X-rays

Proceedings Papers

Numerical Simulation for Nuclear Engineering Education: A Case Study in a Course “Advanced Nuclear Reactor Thermal Analysis”

Shanfang Huang, Yaopeng Gong, Chao Li, Ruilong Liu, Jiageng Wang, Kan Wang

Proc. ASME. ICONE26, Volume 8: Computational Fluid Dynamics (CFD); Nuclear Education and Public Acceptance, V008T12A002, July 22–26, 2018

Paper No: ICONE26-81042

DOI: https://doi.org/10.1115/ICONE26-81042

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Topics: Computer simulation, Education, Nuclear engineering, Nuclear reactors, Thermal analysis, Nuclear power, China, Computer software, Computers, Experimental design

Proceedings Papers

Numerical Study of Water Droplet Heat Removal and Dynamics During its Impact Onto the Micro-Pillar Array at Elevated Temperature

Beni Mehrdad Shahmohammadi, Shangzhen Xie, Jiyun Zhao

Proc. ASME. ICONE26, Volume 7: Decontamination and Decommissioning, Radiation Protection, and Waste Management; Mitigation Strategies for Beyond Design Basis Events, V007T11A001, July 22–26, 2018

Paper No: ICONE26-81171

DOI: https://doi.org/10.1115/ICONE26-81171

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Topics: Columns (Structural), Drops, Dynamics (Mechanics), Heat, Temperature, Water, Cooling, Heat transfer, Computers, Finite element methods

Proceedings Papers

Evolution and Implementation of the Design Extension Conditions (DEC) Concept: Assessment of Selected Events

Pavel Kral

Proc. ASME. ICONE26, Volume 7: Decontamination and Decommissioning, Radiation Protection, and Waste Management; Mitigation Strategies for Beyond Design Basis Events, V007T11A017, July 22–26, 2018

Paper No: ICONE26-82593

DOI: https://doi.org/10.1115/ICONE26-82593

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Topics: Design, Safety, Acceptance criteria, Computers, Fukushima nuclear disaster, Japan, 2011, Nuclear power stations

Proceedings Papers

JSNT-S: A Parallel 3D Discrete Ordinates Radiation Transport Code on Structured Mesh

Tangpei Cheng, Zeyao Mo, Chao Yang, Lili Wen, Li Deng

Proc. ASME. ICONE26, Volume 4: Nuclear Safety, Security, and Cyber Security; Computer Code Verification and Validation, V004T15A017, July 22–26, 2018

Paper No: ICONE26-82252

DOI: https://doi.org/10.1115/ICONE26-82252

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Topics: Radiation (Physics), Algorithms, Computer programming, Computers, Construction

Proceedings Papers

Nuclear Facility Safety Enhancement Using Sandia National Laboratories’ Computer Codes

David L. Y. Louie

Proc. ASME. ICONE26, Volume 4: Nuclear Safety, Security, and Cyber Security; Computer Code Verification and Validation, V004T06A006, July 22–26, 2018

Paper No: ICONE26-81097

DOI: https://doi.org/10.1115/ICONE26-81097

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Topics: Computers, Safety, Fire, Physics, Chemistry, Dynamics (Mechanics), Fluid mechanics, Industrial research, Leakage, Nuclear power stations

Proceedings Papers

Extended Ultimate Response Measures for Offshore Nuclear Power Plant Under Barge-Reactor Coupled Conditions

Jue Wang, Longze Li, Chen Hu, Wang Cong

Proc. ASME. ICONE26, Volume 1: Operations and Maintenance, Engineering, Modifications, Life Extension, Life Cycle, and Balance of Plant; Instrumentation and Control (I&C) and Influence of Human Factors; Innovative Nuclear Power Plant Design and SMRs, V001T13A002, July 22–26, 2018

Paper No: ICONE26-81159

DOI: https://doi.org/10.1115/ICONE26-81159

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Topics: Nuclear power stations, Ocean engineering, Seawater, Boilers, Design, Dimensions, Hazards, Heat, Accidents, Computers

Proceedings Papers

NPP I&C Safety Assessment by Aggregation of Formal Techniques

Eugene Babeshko, Vyacheslav Kharchenko, Kostiantyn Leontiiev, Oleg Odarushchenko, Oleksiy Strjuk

Paper No: ICONE26-82270

DOI: https://doi.org/10.1115/ICONE26-82270

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Topics: Nuclear power stations, Safety, Computer software, Failure mode and effects analysis, Computers, Control systems, Design, Failure mechanisms, Flow (Dynamics), Hardware

Proceedings Papers

Example of Graded and Lifecycle Phase-Specific Security Controls for Nuclear I&C and EPS Use Cases

Venesa Watson, Edita Bajramovic, Xinxin Lou, Karl Waedt

Proc. ASME. ICONE26, Volume 5: Advanced Reactors and Fusion Technologies; Codes, Standards, Licensing, and Regulatory Issues, V005T07A006, July 22–26, 2018

Paper No: ICONE26-81601

DOI: https://doi.org/10.1115/ICONE26-81601

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Topics: Security, Power stations, Computer security, Computers, Electronic systems, Instrumentation, Maintenance, Nuclear power stations, Programmable controllers, Safety

Proceedings Papers

Development of an Optimized Transport Solver in SARAX for Fast Reactor Analysis

Zhitao Xu, Hongchun Wu, Youqi Zheng, Mingtao He

Proc. ASME. ICONE26, Volume 9: Student Paper Competition, V009T16A081, July 22–26, 2018

Paper No: ICONE26-82380

DOI: https://doi.org/10.1115/ICONE26-82380

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Topics: Fast neutron reactors, Geometry, Storage, China, Computers, Elastic scattering, Mean free path, Neutrons, Resonance, Simulation

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Measurement of Two-Phase Flow: Static CT System Based on Carbon Nanotubes

Bubble Boundary Detection Algorithm Without Model Training

Development of the Digital Human-Computer Interaction Platform of the M 2 LFR-1000 Reactor Based on QT and ICoCo

Applying Machine Learning to Improve BOA Analysis of CIPS/CILC

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

Equal Forced Time Step Approach to PSA for a Dynamic System – A Case of the Holdup Tank

RELAP5-3D Sensitivity Studies of Incorporating Axial Boron Gradients Into a Heater Tube Experiment for Pool Boiling CHF Testing in TREAT

Simulation of Severe Accident Progression Using ROSHNI: A New Integrated Simulation Code for PHWR Severe Accidents

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

Research of Fast Modeling and Simulating Platform for Nuclear Power Plant Secondary Loop

Dose Minimization Game for Smartphones

Numerical Simulation for Nuclear Engineering Education: A Case Study in a Course “Advanced Nuclear Reactor Thermal Analysis”

Numerical Study of Water Droplet Heat Removal and Dynamics During its Impact Onto the Micro-Pillar Array at Elevated Temperature

Evolution and Implementation of the Design Extension Conditions (DEC) Concept: Assessment of Selected Events

JSNT-S: A Parallel 3D Discrete Ordinates Radiation Transport Code on Structured Mesh

Nuclear Facility Safety Enhancement Using Sandia National Laboratories’ Computer Codes

Extended Ultimate Response Measures for Offshore Nuclear Power Plant Under Barge-Reactor Coupled Conditions

NPP I&C Safety Assessment by Aggregation of Formal Techniques

Example of Graded and Lifecycle Phase-Specific Security Controls for Nuclear I&C and EPS Use Cases

Development of an Optimized Transport Solver in SARAX for Fast Reactor Analysis

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