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Proceedings Papers

Experimental Study on Measurement of Boiling Entrainment Rate From Falling Liquid Film With Gas Sheared Flow

Raka Firman Baskara Permana, Junpei Tabuchi, Tomio Okawa, Yuki Narushima, Hajime Furuichi, Kenichi Katono

Proc. ASME. ICONE29, Volume 15: Student Paper Competition, V015T16A022, August 8–12, 2022

Paper No: ICONE29-90420

DOI: https://doi.org/10.1115/ICONE29-90420

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Topics: Boiling, Flow (Dynamics), Liquid films, Drops, Heat flux, Two-phase flow, Gas flow, Nucleate boiling, Separation (Technology), Steady state

Proceedings Papers

Safety Evaluation of Flowrate Dissymmetry on Nuclear Power Plant Operation

Dongyuan Li, Jinkai Wang, Jiaoshen Xu, Zengpei Zhu, Yaqi Zhang

Proc. ASME. ICONE29, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A072, August 8–12, 2022

Paper No: ICONE29-93277

DOI: https://doi.org/10.1115/ICONE29-93277

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Topics: Nuclear power plant operations, Nuclear reactor coolants, Nucleate boiling, Safety, Accidents, Flow (Dynamics), Nuclear power stations, Pressurized water reactors, Feedwater, Steam

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

Experiment Investigation on Onset of Flow Instability in Upward Tube Under Low Pressure Condition

Bing Yang, Minfu Zhao, Junhan Wei

Proc. ASME. ICONE29, Volume 7A: Thermal-Hydraulics and Safety Analysis, V07AT07A035, August 8–12, 2022

Paper No: ICONE29-90817

DOI: https://doi.org/10.1115/ICONE29-90817

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Topics: Flow instability, Pressure, Pressure drop, Two-phase flow, Bubbles, Cooling, Flow (Dynamics), Fluids, Heat, Heat flux

Proceedings Papers

Experimental Study of the Onset of Nucleate Boiling in Vertical Rectangular Narrow Channel With Large Aspect Ratio

Cao Chengque, Kuang Bo, Zhao Yu, Deng Jian, Ding Shuhua, Wu Dan

Proc. ASME. ICONE29, Volume 7A: Thermal-Hydraulics and Safety Analysis, V07AT07A042, August 8–12, 2022

Paper No: ICONE29-91523

DOI: https://doi.org/10.1115/ICONE29-91523

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Topics: Nucleate boiling

Proceedings Papers

Baseline WALT DNB Test Results With Cr-Coated Cladding to Support Accident Tolerant Fuel Development

Guoqiang Wang, William A. Byers, Zeses Karoutas

Proc. ASME. ICONE28, Volume 2: Nuclear Fuels, Research, and Fuel Cycle; Nuclear Codes and Standards; Thermal-Hydraulics, V002T07A041, August 4–6, 2021

Paper No: ICONE28-66591

DOI: https://doi.org/10.1115/ICONE28-66591

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Topics: Accidents, Cladding systems (Building), Critical heat flux, Fuels, Chemistry, Pressurized water reactors, Coolants, Electrical resistivity, Film boiling, Heat flux

Proceedings Papers

Experimental Observation of Nucleate Boiling Entrainment in a Liquid Film

Junpei Tabuchi, Yuki Narushima, Kenichi Katono, Tomio Okawa

Proc. ASME. ICONE28, Volume 4: Student Paper Competition, V004T14A020, August 4–6, 2021

Paper No: ICONE28-63813

DOI: https://doi.org/10.1115/ICONE28-63813

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Topics: Liquid films, Nucleate boiling

Proceedings Papers

A New Safety Margin Evaluation Method: Quality Margin Method

Zhao Minfu, Duan Minghui, Lv Yufeng

Proc. ASME. ICONE2020, Volume 3: Student Paper Competition; Thermal-Hydraulics; Verification and Validation, V003T13A003, August 4–5, 2020

Paper No: ICONE2020-16031

DOI: https://doi.org/10.1115/ICONE2020-16031

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Topics: Critical heat flux, Evaluation methods, Safety, Design, Heat, Nucleate boiling, Accidents, Computational methods, Flux (Metallurgy), Heating

Proceedings Papers

Optimization Study for Uncertainty Reduction of In-Pile CHF Experiments in TREAT

Seokbin Seo, Nicholas R. Brown, Robert J. Armstrong, Charles P. Folsom, Colby B. Jensen

Proc. ASME. ICONE2020, Volume 3: Student Paper Competition; Thermal-Hydraulics; Verification and Validation, V003T13A053, August 4–5, 2020

Paper No: ICONE2020-16884

DOI: https://doi.org/10.1115/ICONE2020-16884

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Topics: Critical heat flux, Optimization, Sensitivity analysis, Uncertainty, Coolants, Heat transfer, Transients (Dynamics), Accidents, Fuels, Heat flux

Proceedings Papers

Thermal Safety Margin Calculation of the MP-2 Experiment in the Advanced Test Reactor

Grant L. Hawkes

Proc. ASME. ICONE2020, Volume 3: Student Paper Competition; Thermal-Hydraulics; Verification and Validation, V003T13A030, August 4–5, 2020

Paper No: ICONE2020-16592

DOI: https://doi.org/10.1115/ICONE2020-16592

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Topics: Fuels, Irradiation (Radiation exposure), Safety, Cycles, Plates (structures), Transients (Dynamics), Heat, Aluminum, Finite element analysis, Thermal analysis

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

A Visual Experiment of Single Bubble Growth Processes in a Vertical Rectangular Channel

Ning Cheng, Yun Guo, Changhong Peng

Proc. ASME. ICONE26, Volume 6A: Thermal-Hydraulics and Safety Analyses, V06AT08A035, July 22–26, 2018

Paper No: ICONE26-81415

DOI: https://doi.org/10.1115/ICONE26-81415

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Topics: Bubbles, Fluids, Heating, Nucleation (Physics), Temperature, Flow (Dynamics), Boiling, Nuclear reactors, Nucleate boiling, Shapes

Proceedings Papers

First Attempt to Determine a Critical Heat Flux Correlation for Thermalhydraulic System Codes

Christophe Herer, Antoine Lejosne

Proc. ASME. ICONE26, Volume 6A: Thermal-Hydraulics and Safety Analyses, V06AT08A057, July 22–26, 2018

Paper No: ICONE26-81589

DOI: https://doi.org/10.1115/ICONE26-81589

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Topics: Critical heat flux, Boiling, Fluids, Temperature, Vapors, Nucleate boiling, Uncertainty, Accidents, Cooling, Databases

Proceedings Papers

Study on the Prediction of DNB-Type Critical Heat Flux in Rod Bundle Under Motion Conditions

Siyang Huang, Xiaoyan Wang, Wenxi Tian, Ronghua Chen, Junmei Wu, G. H. Su, Suizheng Qiu

Proc. ASME. ICONE26, Volume 6A: Thermal-Hydraulics and Safety Analyses, V06AT08A050, July 22–26, 2018

Paper No: ICONE26-81544

DOI: https://doi.org/10.1115/ICONE26-81544

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Topics: Critical heat flux, Fuel rods, Flow (Dynamics), Fuels, Vapors, Bubbles, Coolants, Cross-flow, Damage, Failure

Proceedings Papers

Boiling Visualization and Critical Heat Flux (CHF) Phenomena on PCB in a Saturated Pool at Various Surface Orientations

Elvira F. Tanjung, Daeseong Jo

Proc. ASME. ICONE26, Volume 9: Student Paper Competition, V009T16A022, July 22–26, 2018

Paper No: ICONE26-81382

DOI: https://doi.org/10.1115/ICONE26-81382

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Topics: Boiling, Critical heat flux, Visualization, Bubbles, Vapors, Dynamics (Mechanics), Image processing, Photography, Water, Buoyancy

Proceedings Papers

Advances in Modeling Critical Heat Flux in LWR Boiling Flows With the NEK-2P CFD Code

Adrian Tentner, Prasad Vegendla, Ananias Tomboulides, Aleks Obabko, Elia Merzari, Dillon Shaver

Proc. ASME. ICONE26, Volume 8: Computational Fluid Dynamics (CFD); Nuclear Education and Public Acceptance, V008T09A030, July 22–26, 2018

Paper No: ICONE26-81910

DOI: https://doi.org/10.1115/ICONE26-81910

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Topics: Boiling, Computational fluid dynamics, Critical heat flux, Flow (Dynamics), Light water reactors, Modeling, Wall temperature, Heat transfer, Nucleate boiling, Simulation

Proceedings Papers

Moving From V&V to V&V&C in Nuclear Thermal-Hydraulics

Francesco D’Auria, Marco Lanfredini

Proc. ASME. ICONE26, Volume 4: Nuclear Safety, Security, and Cyber Security; Computer Code Verification and Validation, V004T15A019, July 22–26, 2018

Paper No: ICONE26-82574

DOI: https://doi.org/10.1115/ICONE26-82574

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Topics: Density, Film boiling, Flow (Dynamics), Heat flux, High pressure (Physics), Nucleate boiling, Pipes, Power density, Pressure, Temperature

Proceedings Papers

Analysis of Flow Blockage of a Single Fuel Assembly in the JRR-3 20MW Research Reactor

Yuchuan Guo, Guanbo Wang, Dazhi Qian, Heng Yu, Bo Hu

Proc. ASME. ICONE26, Volume 6A: Thermal-Hydraulics and Safety Analyses, V06AT08A030, July 22–26, 2018

Paper No: ICONE26-81313

DOI: https://doi.org/10.1115/ICONE26-81313

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Topics: Flow (Dynamics), Fuels, Manufacturing, Accidents, Scram, Coolants, Hydraulic drive systems, Nucleate boiling, Plates (structures), Temperature

Proceedings Papers

A Brief Review of Computational Intelligence Techniques for Critical Heat Flux Prediction

B. T. Jiang, Y. N. Liu

Proc. ASME. ICONE26, Volume 6B: Thermal-Hydraulics and Safety Analyses, V06BT08A050, July 22–26, 2018

Paper No: ICONE26-82325

DOI: https://doi.org/10.1115/ICONE26-82325

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Topics: Critical heat flux, Design, Nuclear reactors, Artificial neural networks, Fuel rods, Nuclear power stations, Safety, Temperature, Water, Economics

Proceedings Papers

Sensitivity of CTF Solution to Subchannel Window Size

Roman Mukin, Marcus Seidl, Ivor Clifford, Hakim Ferroukhi

Proc. ASME. ICONE26, Volume 6B: Thermal-Hydraulics and Safety Analyses, V06BT08A065, July 22–26, 2018

Paper No: ICONE26-82546

DOI: https://doi.org/10.1115/ICONE26-82546

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Topics: Critical heat flux, Displacement, Flow (Dynamics), Fuels, Heat flux, Modeling, Nucleate boiling, Pressurized water reactors

2 3 4 5

NARROW

Experimental Study on Measurement of Boiling Entrainment Rate From Falling Liquid Film With Gas Sheared Flow

Safety Evaluation of Flowrate Dissymmetry on Nuclear Power Plant Operation

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

Experiment Investigation on Onset of Flow Instability in Upward Tube Under Low Pressure Condition

Experimental Study of the Onset of Nucleate Boiling in Vertical Rectangular Narrow Channel With Large Aspect Ratio

Baseline WALT DNB Test Results With Cr-Coated Cladding to Support Accident Tolerant Fuel Development

Experimental Observation of Nucleate Boiling Entrainment in a Liquid Film

A New Safety Margin Evaluation Method: Quality Margin Method

Optimization Study for Uncertainty Reduction of In-Pile CHF Experiments in TREAT

Thermal Safety Margin Calculation of the MP-2 Experiment in the Advanced Test Reactor

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

A Visual Experiment of Single Bubble Growth Processes in a Vertical Rectangular Channel

First Attempt to Determine a Critical Heat Flux Correlation for Thermalhydraulic System Codes

Study on the Prediction of DNB-Type Critical Heat Flux in Rod Bundle Under Motion Conditions

Boiling Visualization and Critical Heat Flux (CHF) Phenomena on PCB in a Saturated Pool at Various Surface Orientations

Advances in Modeling Critical Heat Flux in LWR Boiling Flows With the NEK-2P CFD Code

Moving From V&V to V&V&C in Nuclear Thermal-Hydraulics

Analysis of Flow Blockage of a Single Fuel Assembly in the JRR-3 20MW Research Reactor

A Brief Review of Computational Intelligence Techniques for Critical Heat Flux Prediction

Sensitivity of CTF Solution to Subchannel Window Size

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