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Proceedings Papers

Apros-Based Loviisa NPP Full Scope Training Simulator and Engineering Model

Arttu Meriläinen, Olli Viljakainen, Karri Honkoila, Ari Lahtela

Proc. ASME. ICONE28, Volume 1: Operating Plant Challenges, Successes, and Lessons Learned; Nuclear Plant Engineering; Advanced Reactors and Fusion; Small Modular and Micro-Reactors Technologies and Applications, V001T01A004, August 4–6, 2021

Paper No: ICONE28-64294

DOI: https://doi.org/10.1115/ICONE28-64294

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Topics: Engineering models, Nuclear power stations, Accidents, Circuits, Accident management, Computer software, Containment, Design, Diesel generators, Electronic systems

Proceedings Papers

Level 2 Probability Safety Assessment for External Events: Approach and Application for NPPs in China

Yu Liu, Cong Wang, Jing Liu, Heng Gao

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, V003T13A001, August 4–6, 2021

Paper No: ICONE28-64329

DOI: https://doi.org/10.1115/ICONE28-64329

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Topics: China, Nuclear power stations, Probability, Safety, Computer software, Fukushima nuclear disaster, Japan, 2011, Pressurized water reactors, Radioactive substances, Risk, Tsunamis

Proceedings Papers

Wall Materials Effects on Sheltered Indoor Doses From an SMR Hypothetical Accident Release

Yamato Sugitatsu, Shripad T. Revankar

Proc. ASME. ICONE28, Volume 4: Student Paper Competition, V004T14A004, August 4–6, 2021

Paper No: ICONE28-62097

DOI: https://doi.org/10.1115/ICONE28-62097

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Topics: Accidents, Emergency management, Evacuations, Small modular reactors, Computer software, Coolants, Emergencies, Emergency response, Monte Carlo methods, Protective actions

Proceedings Papers

Numerical Analysis of Pressurized Thermal Shock in Reactor Pressure Vessel

Yubin Zhang

Paper No: ICONE28-64737

DOI: https://doi.org/10.1115/ICONE28-64737

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Topics: Numerical analysis, Reactor vessels, Thermal shock, Accidents, Computational fluid dynamics, Computer software, Coolants, Flow (Dynamics), Mechanical structures, Nozzles

Proceedings Papers

Migration Characteristics of Sub-Source Items in Breach Occurrences

Xu Peng, Tian Ruifeng

Paper No: ICONE28-64606

DOI: https://doi.org/10.1115/ICONE28-64606

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Topics: Accidents, Aerosols, Computational fluid dynamics, Computer software, Coolants, Drag (Fluid dynamics), Flow (Dynamics), Fluids, Gravity (Force), Hazards

Proceedings Papers

Optimal Design for Helium Cooled Solid Breeder Blanket of CFETR

Jose A. Nogueron, Zhang Baorui, Zhou Zhiwei

Proc. ASME. ICONE2020, Volume 2: Nuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors, V002T11A008, August 4–5, 2020

Paper No: ICONE2020-16345

DOI: https://doi.org/10.1115/ICONE2020-16345

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Topics: Cooling, Design, Helium, Tokamaks, Computational fluid dynamics, Bridges (Structures), China, Combustion, Computer software, Cycles

Proceedings Papers

FUELPOOL: A Computer Program to Model CANDU Spent Fuel Pool Severe Accident Progression and Consequences

Yong Mann Song, Jong Yeob Jung, Sunil Nijhawan

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, V001T01A015, August 4–5, 2020

Paper No: ICONE2020-16634

DOI: https://doi.org/10.1115/ICONE2020-16634

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Topics: Accidents, Computer software, Spent nuclear fuels, Fuels, Fluids, Heavy water reactors, Radiation (Physics), Stainless steel, Steel, Water

Proceedings Papers

Experimental and Numerical Investigation of Thermal Performance of Synthetic Jet Impingement

Pushpanjay K. Singh, Rohit Kothari, Santosh K. Sahu, Prabhat K. Upadhyay, Shashwat Singh

Paper No: ICONE2020-16775

DOI: https://doi.org/10.1115/ICONE2020-16775

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Topics: Computation, Computer cooling, Computer simulation, Computer software, Diaphragms (Mechanical devices), Diaphragms (Structural), Electromagnetic actuators, Excitation, Flow (Dynamics), Geometry

Proceedings Papers

Review of Application on Dynamic Fault Tree Method in Nuclear Power Plants

Wu Guohua, Yuan Diping, Xiao Yiqing, Wang Jiaxin

Paper No: ICONE2020-16191

DOI: https://doi.org/10.1115/ICONE2020-16191

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Topics: Nuclear power stations, Chain, Explosions, Computer software, Failure, Probabilistic risk assessment

Proceedings Papers

Cyber Resilience Analysis of SCADA Systems in Nuclear Power Plants

Meghan Galiardi, Amanda Gonzales, Jamie Thorpe, Eric Vugrin, Raymond Fasano, Christopher Lamb

Paper No: ICONE2020-16071

DOI: https://doi.org/10.1115/ICONE2020-16071

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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

Development and Verification of PWR Physical and Thermal Coupling Calculation Software

Zhigang Li

Paper No: ICONE2020-16106

DOI: https://doi.org/10.1115/ICONE2020-16106

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Topics: Computer software, Cylinders, Heat conduction, Pressurized water reactors

Proceedings Papers

Numerical Simulation Method Research on Pellet-Cladding Mechanical Interaction Based on ABAQUS Software

Changbing Tang, Yongjun Jiao, Yuanming Li, Yi Zhou, Kun Zhang

Paper No: ICONE2020-16387

DOI: https://doi.org/10.1115/ICONE2020-16387

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Topics: Cladding systems (Building), Computer simulation, Computer software, Fuel rods, Fuels, Stress, Failure, Pressure, Simulation, Transients (Dynamics)

Proceedings Papers

Comparative Thermal Analyses Between Theoretical Mode and RELAP5 Code Simulation for OTSG of a Small PWR

Baihui Jiang, Zhiwei Zhou, Zhaoyang Xia, Qian Sun

Proc. ASME. ICONE2020, Volume 3: Student Paper Competition; Thermal-Hydraulics; Verification and Validation, V003T12A018, August 4–5, 2020

Paper No: ICONE2020-16281

DOI: https://doi.org/10.1115/ICONE2020-16281

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Topics: Boilers, Circuits, Computer software, Construction, Design, Fluids, Heat, Heat transfer, Heat transfer coefficients, Light water reactors

Proceedings Papers

Power Rising and Descending Transient for the OTSG of a Small PWR

Baihui Jiang, Zhiwei Zhou, Zhaoyang Xia, Qian Sun

Proc. ASME. ICONE2020, Volume 3: Student Paper Competition; Thermal-Hydraulics; Verification and Validation, V003T12A019, August 4–5, 2020

Paper No: ICONE2020-16294

DOI: https://doi.org/10.1115/ICONE2020-16294

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Topics: Flow instability, Pressurized water reactors, Transients (Dynamics), Boilers, Flow (Dynamics), Stability, Two-phase flow, Computer software, Fluids, Heat transfer

Proceedings Papers

Development of a Selection Tool for Choosing Decontamination Technology for Canadian Applications

Raj Khurmi, Richard Carlisle, Glenn Harvel

Proc. ASME. ICONE2020, Volume 3: Student Paper Competition; Thermal-Hydraulics; Verification and Validation, V003T12A043, August 4–5, 2020

Paper No: ICONE2020-16760

DOI: https://doi.org/10.1115/ICONE2020-16760

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Topics: Computer software, Decontamination, Nuclear decommissioning

Proceedings Papers

Metamorphic Testing on Nuclide Inventory Tool

Meng Li, Shiyu Yan, Xiaohua Yang, Jie Liu

Proc. ASME. ICONE2020, Volume 3: Student Paper Competition; Thermal-Hydraulics; Verification and Validation, V003T14A001, August 4–5, 2020

Paper No: ICONE2020-16403

DOI: https://doi.org/10.1115/ICONE2020-16403

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Topics: Nuclides, Testing, Algorithms, Approximation, Computer software, Nuclear magnetic resonance, Physics, Software development

Proceedings Papers

Research on Auxiliary Bearing Structure With Buffer Shim Based on LS-DYNA for Helium Circulator of HTR-10

Guojun Yang, Zhe Sun, Xingnan Liu, Zhengang Shi

Proc. ASME. ICONE26, Volume 2: Plant Systems, Structures, Components, and Materials; Risk Assessments and Management, V002T03A013, July 22–26, 2018

Paper No: ICONE26-81304

DOI: https://doi.org/10.1115/ICONE26-81304

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Topics: Bearings, Helium, Polishing equipment, Rotors, Stress, Damage, Stress concentration, Computer software, Deformation, Finite element methods

Proceedings Papers

Preliminary Design Considerations of He-Xe Mixture Cooled Space Nuclear Reactor

Tao Meng, Sichao Tan, Yuhao He, Dongdong Yuan, Kun Cheng

Proc. ASME. ICONE26, Volume 9: Student Paper Competition, V009T16A012, July 22–26, 2018

Paper No: ICONE26-81226

DOI: https://doi.org/10.1115/ICONE26-81226

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Topics: Design, Nuclear reactors, Compressors, Computer software, Heat pipes, Industrial research, Neutrons, Nuclear weapons, Optimization, System efficiency

Proceedings Papers

CFD Investigation of Thermal-Hydraulic Behaviors in Full Reactor Core for Sodium-Cooled Fast Reactor

Jing Chen, Dalin Zhang, Suizheng Qiu, Kui Zhang, Mingjun Wang, G. H. Su

Proc. ASME. ICONE26, Volume 9: Student Paper Competition, V009T16A040, July 22–26, 2018

Paper No: ICONE26-81626

DOI: https://doi.org/10.1115/ICONE26-81626

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Topics: Computational fluid dynamics, Sodium fast reactors, Flow (Dynamics), China, Computer software, Coolants, Design, Fast neutron reactors, Fluids, Heat

Proceedings Papers

Numerical Research on Fuel Rod Progression During Core Degradation Process Using MELCOR

Tangtao Feng, Wenxi Tian, Ping Song, Jun Wang, Mingjun Wang, G. H. Su, Suizheng Qiu

Proc. ASME. ICONE26, Volume 9: Student Paper Competition, V009T16A049, July 22–26, 2018

Paper No: ICONE26-81738

DOI: https://doi.org/10.1115/ICONE26-81738

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Topics: Fuel rods, Accidents, Computer software, High temperature, Hydrogen, Nuclear fuels, Numerical analysis, Temperature, Transients (Dynamics), Tungsten

2 3 4 5

NARROW

Apros-Based Loviisa NPP Full Scope Training Simulator and Engineering Model

Level 2 Probability Safety Assessment for External Events: Approach and Application for NPPs in China

Wall Materials Effects on Sheltered Indoor Doses From an SMR Hypothetical Accident Release

Numerical Analysis of Pressurized Thermal Shock in Reactor Pressure Vessel

Migration Characteristics of Sub-Source Items in Breach Occurrences

Optimal Design for Helium Cooled Solid Breeder Blanket of CFETR

FUELPOOL: A Computer Program to Model CANDU Spent Fuel Pool Severe Accident Progression and Consequences

Experimental and Numerical Investigation of Thermal Performance of Synthetic Jet Impingement

Review of Application on Dynamic Fault Tree Method in Nuclear Power Plants

Cyber Resilience Analysis of SCADA Systems in Nuclear Power Plants

Development and Verification of PWR Physical and Thermal Coupling Calculation Software

Numerical Simulation Method Research on Pellet-Cladding Mechanical Interaction Based on ABAQUS Software

Comparative Thermal Analyses Between Theoretical Mode and RELAP5 Code Simulation for OTSG of a Small PWR

Power Rising and Descending Transient for the OTSG of a Small PWR

Development of a Selection Tool for Choosing Decontamination Technology for Canadian Applications

Metamorphic Testing on Nuclide Inventory Tool

Research on Auxiliary Bearing Structure With Buffer Shim Based on LS-DYNA for Helium Circulator of HTR-10

Preliminary Design Considerations of He-Xe Mixture Cooled Space Nuclear Reactor

CFD Investigation of Thermal-Hydraulic Behaviors in Full Reactor Core for Sodium-Cooled Fast Reactor

Numerical Research on Fuel Rod Progression During Core Degradation Process Using MELCOR

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