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Proceedings Papers

Comparative Machine Learning Study for Estimating Peak Cladding Temperature in AP1000 Under LOFW

Merouane Najar, He Wang

Proc. ASME. ICONE29, Volume 5: Nuclear Safety, Security, and Cyber Security, V005T05A022, August 8–12, 2022

Paper No: ICONE29-91516

DOI: https://doi.org/10.1115/ICONE29-91516

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Topics: Cladding systems (Building), Machine learning, Temperature, Algorithms, Uncertainty quantification, Accidents, Safety, Uncertainty, Databases, Errors

Proceedings Papers

Research on Smart Nuclear Power Construction Based on Digitalization and System Engineering in TNPS

Qiang Yang

Proc. ASME. ICONE29, Volume 12: Innovative and Smart Nuclear Power Plant Design, V012T12A007, August 8–12, 2022

Paper No: ICONE29-91570

DOI: https://doi.org/10.1115/ICONE29-91570

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Topics: Nuclear construction, Systems engineering, Construction, Design, Testing, Nuclear power, Decision making, Dimensions, Nuclear power stations, Power stations

Proceedings Papers

The Evaluation System Study on Layout Design of EMIT Activities in Nuclear Power Plant

Zhou Yikun, Ding Nan, Chen Chengzhen

Proc. ASME. ICONE29, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A083, August 8–12, 2022

Paper No: ICONE29-93429

DOI: https://doi.org/10.1115/ICONE29-93429

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Topics: Design, Inspection, Maintenance, Nuclear power stations, Testing

Proceedings Papers

Potential Crud Related Margin Gains With Chromium Coated Zirconium Cladding

William A. Byers, Guoqiang Wang

Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A094, August 8–12, 2022

Paper No: ICONE29-94477

DOI: https://doi.org/10.1115/ICONE29-94477

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Topics: Cladding systems (Building), Zirconium, Corrosion, Coating processes, Coatings, Fuels, Pressurized water reactors, Accidents, Boiling, Boron

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

Irradiation Induced Crosslinking in “Green” Polylactic-Acid (PLA) Polymers for Enhanced Strength and Elevated Temperature Applications

W. Jiang, A. Bakken, R. P. Taleyarkhan

Proc. ASME. ICONE2020, Volume 3: Student Paper Competition; Thermal-Hydraulics; Verification and Validation, V003T12A044, August 4–5, 2020

Paper No: ICONE2020-16767

DOI: https://doi.org/10.1115/ICONE2020-16767

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Topics: Adhesives, Irradiation (Radiation exposure), Polymers, Temperature, Photons, Testing, Accidents, Bond strength, Bonding, Construction

Proceedings Papers

Thermal-Hydraulic Investigations of a Horizontal Dry Cask Simulator

Ramon J. M. Pulido, Eric R. Lindgren, Samuel G. Durbin, Alex Salazar

Proc. ASME. ICONE2020, Volume 3: Student Paper Competition; Thermal-Hydraulics; Verification and Validation, V003T13A031, August 4–5, 2020

Paper No: ICONE2020-16598

DOI: https://doi.org/10.1115/ICONE2020-16598

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Topics: Air flow, Cladding systems (Building), Cooling, Gases, Heat conduction, Model validation, Physics, Spent nuclear fuels, Storage, Temperature

Proceedings Papers

Study on Natural Circulation Flow Instabilities in Rod Bundle Channel Under Rolling Condition

Kun Cheng, Jian Deng, Rong Cai, Libo Qian, Peiyao Qi, Bingzheng Ke

Proc. ASME. ICONE2020, Volume 3: Student Paper Competition; Thermal-Hydraulics; Verification and Validation, V003T13A020, August 4–5, 2020

Paper No: ICONE2020-16362

DOI: https://doi.org/10.1115/ICONE2020-16362

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Topics: Flow instability, Fuel rods, Oscillations, Flow (Dynamics), Heating, Pressure, Subcooling, Testing, Two-phase flow, Vapors

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

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

Computational Modeling of Terry Turbine Airflow Testing to Support the Expansion of Operating Band in Beyond Design Basis Conditions

Lindsay N. Gilkey, Nathan Andrews, Kyle Ross, Matthew Solom

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, V001T01A012, August 4–5, 2020

Paper No: ICONE2020-16547

DOI: https://doi.org/10.1115/ICONE2020-16547

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Topics: Air flow, Computer simulation, Design, Testing, Turbines, Modeling, Batteries, Accidents, Safety, Water

Proceedings Papers

Use of Micro-Gravity Sensors for External Fluid Level Monitoring in Waste and Nuclear Related Applications

Jeff Ridgway, Bryant Slater

Proc. ASME. ICONE2020, Volume 2: Nuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors, V002T08A058, August 4–5, 2020

Paper No: ICONE2020-16810

DOI: https://doi.org/10.1115/ICONE2020-16810

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Topics: Fluids, Gravity (Force), Sensors, Vessels, Leakage, Nuclear power, Sensor placement, Simulation, Accuracy and precision, Algorithms

Proceedings Papers

Modeling the Molten Salt Reactor Experiment With the GOTHIC Code

Rodney Harvill, Jeff Lane, John Link, Anita Gates, Tom Kindred

Paper No: ICONE2020-16058

DOI: https://doi.org/10.1115/ICONE2020-16058

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Topics: Design, Modeling, Molten salt reactors, Heat, Fuels, Neutrons, Transients (Dynamics), Flow (Dynamics), Fluids, Nuclear fission

Proceedings Papers

Determining Airborne Release Fraction From DOT 7A Drums Exposed to a Thermal Insult

Hector Mendoza, Victor G. Figueroa, Walter Gill, Scott Sanborn

Paper No: ICONE2020-16755

DOI: https://doi.org/10.1115/ICONE2020-16755

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Topics: Accidents, Filters, Fire, Liquid pool fires, Radiant heat, Radioactive substances, Safety, Stress, Testing, Thermogravimetry

Proceedings Papers

Development and Assessment of a Nearly Autonomous Management and Control System During a Single Loss of Flow Accident

Linyu Lin, Paridhi Athe, Pascal Rouxelin, Nam Dinh, Jeffrey Lane

Paper No: ICONE2020-16908

DOI: https://doi.org/10.1115/ICONE2020-16908

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Topics: Accidents, Control systems, Flow (Dynamics), Workflow, Databases, Safety, Breeder reactors, Decision making, Design, Engines

Proceedings Papers

Experimental Study on Spray Pattern of Pressure-Swirl Nozzle in Reactor Containment

Jiawei Bian, Dalin Zhang, Rulei Sun, Yingwei Wu, Wenxi Tian, G. H. Su, Suizheng Qiu

Proc. ASME. ICONE26, Volume 9: Student Paper Competition, V009T16A033, July 22–26, 2018

Paper No: ICONE26-81505

DOI: https://doi.org/10.1115/ICONE26-81505

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Topics: Containment, Nozzles, Pressure, Sprays, Plasma spraying, Spraying (Coating processes), Design, Drops, Optimization, Pressurized water reactors

Proceedings Papers

Design for Plant Modularisation: Nuclear and SMR

Paul Wrigley, Paul Wood, Paul Stewart, Richard Hall, Dan Robertson

Proc. ASME. ICONE26, Volume 9: Student Paper Competition, V009T16A051, July 22–26, 2018

Paper No: ICONE26-81760

DOI: https://doi.org/10.1115/ICONE26-81760

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Topics: Design, Chemical processes, Circuits, Design engineering, Nuclear physics, Nuclear power, Safety, Small modular reactors, Steam, Testing

Proceedings Papers

RCIC Turbo-Pump Scaling Through CFD and Model Testing for the Texas A&M University NHTS Facility

Mohammad A. Hawila, Karen Vierow Kirkland

Proc. ASME. ICONE26, Volume 9: Student Paper Competition, V009T16A008, July 22–26, 2018

Paper No: ICONE26-81119

DOI: https://doi.org/10.1115/ICONE26-81119

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Topics: Computational fluid dynamics, Pumps, Testing, Turbochargers, Test facilities, Design, Engineering simulation, Nuclear power stations, Simulation, Turbines

Proceedings Papers

TREAT Transient Modeling and Impact of Graphite Thermal Scattering

Nina C. Sorrell, Ayman I. Hawari

Proc. ASME. ICONE26, Volume 9: Student Paper Competition, V009T16A062, July 22–26, 2018

Paper No: ICONE26-81887

DOI: https://doi.org/10.1115/ICONE26-81887

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Topics: Electromagnetic scattering, Graphite, Modeling, Radiation scattering, Scattering (Physics), Transients (Dynamics), Simulation, Temperature, Fuels, Cross section (Physics)

Proceedings Papers

CFD Modelling of Loss of Vacuum Accident (LOVA) for CFETR

Youyou Xu, Songlin Liu, Xiaoman Cheng, Xuebin Ma

Proc. ASME. ICONE26, Volume 8: Computational Fluid Dynamics (CFD); Nuclear Education and Public Acceptance, V008T09A032, July 22–26, 2018

Paper No: ICONE26-81970

DOI: https://doi.org/10.1115/ICONE26-81970

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Topics: Accidents, Computational fluid dynamics, Modeling, Vacuum, Air flow, Dust, Leakage, Maintenance, Bridges (Structures), China

NARROW

Comparative Machine Learning Study for Estimating Peak Cladding Temperature in AP1000 Under LOFW

Research on Smart Nuclear Power Construction Based on Digitalization and System Engineering in TNPS

The Evaluation System Study on Layout Design of EMIT Activities in Nuclear Power Plant

Potential Crud Related Margin Gains With Chromium Coated Zirconium Cladding

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

Irradiation Induced Crosslinking in “Green” Polylactic-Acid (PLA) Polymers for Enhanced Strength and Elevated Temperature Applications

Thermal-Hydraulic Investigations of a Horizontal Dry Cask Simulator

Study on Natural Circulation Flow Instabilities in Rod Bundle Channel Under Rolling Condition

Metamorphic Testing on Nuclide Inventory Tool

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

Computational Modeling of Terry Turbine Airflow Testing to Support the Expansion of Operating Band in Beyond Design Basis Conditions

Use of Micro-Gravity Sensors for External Fluid Level Monitoring in Waste and Nuclear Related Applications

Modeling the Molten Salt Reactor Experiment With the GOTHIC Code

Determining Airborne Release Fraction From DOT 7A Drums Exposed to a Thermal Insult

Development and Assessment of a Nearly Autonomous Management and Control System During a Single Loss of Flow Accident

Experimental Study on Spray Pattern of Pressure-Swirl Nozzle in Reactor Containment

Design for Plant Modularisation: Nuclear and SMR

RCIC Turbo-Pump Scaling Through CFD and Model Testing for the Texas A&M University NHTS Facility

TREAT Transient Modeling and Impact of Graphite Thermal Scattering

CFD Modelling of Loss of Vacuum Accident (LOVA) for CFETR

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