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Proceedings Papers

Development of Effective Momentum Model for Steam Injection Through Multi-Hole Spargers: Unit Cell Model

Xicheng Wang, Dmitry Grishchenko, Pavel Kudinov

Proc. ASME. ICONE28, Volume 4: Student Paper Competition, V004T14A084, August 4–6, 2021

Paper No: ICONE28-65751

DOI: https://doi.org/10.1115/ICONE28-65751

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Topics: Condensation, Environmental health and safety, Momentum, Steam, Thermal stratification, Turbulence, Heat, Boundary-value problems, Containment, Modeling

Proceedings Papers

Numerical Analysis of Pressurized Thermal Shock in Reactor Pressure Vessel

Yubin Zhang

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, V003T08A011, August 4–6, 2021

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

Development of Effective Momentum Model for Steam Injection Through Multi-Hole Spargers Using a Condensation Region Approach

Xicheng Wang, Dmitry Grishchenko, Pavel Kudinov

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, V001T03A025, August 4–5, 2020

Paper No: ICONE2020-16852

DOI: https://doi.org/10.1115/ICONE2020-16852

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Topics: Computational fluid dynamics, Condensation, Momentum, Steam, Thermal stratification

Proceedings Papers

Experimental Investigations on Thermal Stratification in a Large Pool of Water With Immersed Isolation Condenser

Sunil Kumar, P. K. Vijayan, R. B. Grover, U. Kannan, Harekrishna Yadav, A. Agrawal

Proc. ASME. ICONE2020, Volume 3: Student Paper Competition; Thermal-Hydraulics; Verification and Validation, V003T13A033, August 4–5, 2020

Paper No: ICONE2020-16647

DOI: https://doi.org/10.1115/ICONE2020-16647

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Topics: Condensers (steam plant), Thermal stratification, Water, Heat, Heat exchangers, Boiling, Density, Gravity (Force), Heavy water reactors, Hot water

Proceedings Papers

Development of Evaluation Method for Thermal Stratification by Cavity Flow in a Vertical Branch Pipe With Elbow and Horizontal Section: Experimental Results

Atsushi Kodama, Yoshiteru Komuro, Keiichi Hori, Hironori Noguchi, Yoshiyuki Kondo, Koichi Tanimoto

Proc. ASME. ICONE26, Volume 6A: Thermal-Hydraulics and Safety Analyses, V06AT08A014, July 22–26, 2018

Paper No: ICONE26-81143

DOI: https://doi.org/10.1115/ICONE26-81143

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Topics: Cavity flows, Evaluation methods, Pipes, Thermal stratification, Flow (Dynamics), Water, Fatigue, High temperature, Temperature, Temperature profiles

Proceedings Papers

Development of Evaluation Method for Thermal Stratification by Cavity Flow in a Vertical Branch Pipe With Elbow and Horizontal Section: Modeling of Evaluation Method

Atsushi Kodama, Yoshiteru Komuro, Keiichi Hori, Hironori Noguchi, Yoshiyuki Kondo, Koichi Tanimoto

Proc. ASME. ICONE26, Volume 6A: Thermal-Hydraulics and Safety Analyses, V06AT08A015, July 22–26, 2018

Paper No: ICONE26-81144

DOI: https://doi.org/10.1115/ICONE26-81144

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Topics: Cavity flows, Evaluation methods, Modeling, Pipes, Thermal stratification, Fatigue, High temperature, Temperature, Water, Cycles

Proceedings Papers

Two Phase Flow Behavior During Pool Scrubbing

Yuki Nakamura, Kota Fujiwara, Wataru Kikuchi, Shimpei Saito, Tomohisa Yuasa, Akiko Kaneko, Yutaka Abe

Proc. ASME. ICONE26, Volume 9: Student Paper Competition, V009T16A032, July 22–26, 2018

Paper No: ICONE26-81497

DOI: https://doi.org/10.1115/ICONE26-81497

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Topics: Two-phase flow, Bubbles, Water, Flow (Dynamics), Accidents, Nozzles, Particulate matter, Thermal stratification, Decontamination, Steam

Proceedings Papers

Thermal Stratification Modeling for Sodium-Cooled Fast Reactors: A Status Update

Sarah Morgan, Sama Bilbao y Leon, Matthew Bucknor, Mark Anderson, Emilio Baglietto, James Schneider, Matthew Weathered, Liangyu Xu

Proc. ASME. ICONE26, Volume 9: Student Paper Competition, V009T16A078, July 22–26, 2018

Paper No: ICONE26-82364

DOI: https://doi.org/10.1115/ICONE26-82364

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Topics: Modeling, Sodium fast reactors, Thermal stratification, Computational fluid dynamics, Accidents, Design, Licensing, Power stations, Uncertainty

Proceedings Papers

Validation of a Code and Effect of Turbulence Model on Predicting Thermal Stratification Phenomena in the Upper Plenum of SFR

Shibao Wang, Dalin Zhang, Chenglong Wang, Ping Song, Jing Chen, Suizheng Qiu, Guanghui Su

Proc. ASME. ICONE26, Volume 9: Student Paper Competition, V009T16A035, July 22–26, 2018

Paper No: ICONE26-81551

DOI: https://doi.org/10.1115/ICONE26-81551

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Topics: Sodium fast reactors, Thermal stratification, Turbulence, Sodium, Momentum, Breeder reactors, Buoyancy, Convection, Deformation, Diffusion (Physics)

Proceedings Papers

A Validation of RELAP on Predicting Nuclear Power Plant Phenomena

Ji Soo Ahn, Michael Bluck, Matthew Eaton, Chris Jackson

Proc. ASME. ICONE26, Volume 4: Nuclear Safety, Security, and Cyber Security; Computer Code Verification and Validation, V004T15A006, July 22–26, 2018

Paper No: ICONE26-81424

DOI: https://doi.org/10.1115/ICONE26-81424

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Topics: Nuclear power stations, Thermal stratification, Pipes, Surges, Computational fluid dynamics, Cooling, Errors, Feedwater, Junctions, Piping systems

Proceedings Papers

Numerical Simulation for Effect of Rolling Motion on Thermal Stratification in a Surge Line

Y. L. Shen, Tao Lu, Bo Liu

Proc. ASME. ICONE25, Volume 8: Computational Fluid Dynamics (CFD) and Coupled Codes; Nuclear Education, Public Acceptance and Related Issues, V008T09A033, July 2–6, 2017

Paper No: ICONE25-67026

DOI: https://doi.org/10.1115/ICONE25-67026

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Topics: Computer simulation, Surges, Thermal stratification, Temperature, Computational fluid dynamics, Fluids, Pipes, Temperature distribution, Degrees of freedom, Fatigue

Proceedings Papers

Numerical Simulation of Fluid Mixing and Stratification in Large Space

Xingdi Cao, Fenglei Niu, Bin Wang, Xiaowei Su

Proc. ASME. ICONE25, Volume 8: Computational Fluid Dynamics (CFD) and Coupled Codes; Nuclear Education, Public Acceptance and Related Issues, V008T09A028, July 2–6, 2017

Paper No: ICONE25-66840

DOI: https://doi.org/10.1115/ICONE25-66840

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Topics: Computer simulation, Containment, Cooling systems, Density, Design, Fluids, Heat, Optimization, Safety, Temperature

Proceedings Papers

Thermal Stratification Analysis and Fatigue Evaluation for Pressurizer Surge Line in Nuclear Power Plant

Xiao Xu, Pan Liu, Guihe Zhang, Dasheng Wang, Ting Jin

Proc. ASME. ICONE25, Volume 2: Plant Systems, Structures, Components and Materials, V002T03A082, July 2–6, 2017

Paper No: ICONE25-67118

DOI: https://doi.org/10.1115/ICONE25-67118

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Topics: Fatigue, Nuclear power stations, Surges, Thermal stratification, Stress, Dimensions, Boundary layers, Fluids, Numerical analysis, Temperature

Proceedings Papers

Experimental Investigation on the Pipe Leakage

Benan Cai, Qi Zhang, Yu Weng, Hongfang Gu, Haijun Wang

Proc. ASME. ICONE25, Volume 4: Nuclear Safety, Security, Non-Proliferation and Cyber Security; Risk Management, V004T06A026, July 2–6, 2017

Paper No: ICONE25-67251

DOI: https://doi.org/10.1115/ICONE25-67251

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Topics: Leakage, Pipes, Temperature, Fracture (Materials), Pipelines, Nuclear power stations, High temperature, Fatigue, Fluids, High pressure (Physics)

Proceedings Papers

The Experimental Study on Stratification and Transport of Hydrogen in the Containment With Light Non-Condensable Gas

Xiaobo Lee, Xuefeng Lyu, Ke Ji

Proc. ASME. ICONE25, Volume 4: Nuclear Safety, Security, Non-Proliferation and Cyber Security; Risk Management, V004T14A025, July 2–6, 2017

Paper No: ICONE25-66833

DOI: https://doi.org/10.1115/ICONE25-66833

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Topics: Containment, Hydrogen, Domes (Structural elements), Helium, Sprays, Buoyancy, China, Containers, Drops, Electricity (Physics)

Proceedings Papers

Method for Measuring Temperature of Inner Wall Surface of Pipeline in Nuclear Power Plant

Ling Jun, Wang Hai-jun, Liu Lang, Chen Tong, Liu Hong-tao, He Da-yu

Proc. ASME. ICONE25, Volume 1: Operations and Maintenance, Engineering, Modifications, Life Extension, Life Cycle and Balance of Plant; I&C, Digital Controls, and Influence of Human Factors, V001T01A041, July 2–6, 2017

Paper No: ICONE25-67553

DOI: https://doi.org/10.1115/ICONE25-67553

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Topics: Nuclear power stations, Pipelines, Temperature measurement, Temperature, Fatigue, Fluctuations (Physics), Pipes, Energy conservation, Fluids, Heat

Proceedings Papers

The Effect of IRWST Simulation Method on the Analysis of Small Break LOCA Using RELAP5

Caihong Xu, Guobao Shi, Kemei Cao, Xiaoyu Cai, Zhanfei Qi

Proc. ASME. ICONE25, Volume 6: Thermal-Hydraulics, V006T08A012, July 2–6, 2017

Paper No: ICONE25-66219

DOI: https://doi.org/10.1115/ICONE25-66219

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Topics: Simulation, Flow (Dynamics), Heat, Nuclear power stations, Safety, Accidents, Containment, Coolants, Cooling, Heat exchangers

Proceedings Papers

Investigation on Accident Progression and Melt Behavior at the Fukushima Daiichi Units 1 and 2 Using MELCOR Code

Gen Li, Shan Zheng, Akifumi Yamaji, Daotong Chong, Junjie Yan

Proc. ASME. ICONE25, Volume 6: Thermal-Hydraulics, V006T08A029, July 2–6, 2017

Paper No: ICONE25-66389

DOI: https://doi.org/10.1115/ICONE25-66389

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Topics: Accidents, Fukushima nuclear disaster, Japan, 2011, Modeling, Failure, Failure mechanisms, Floods, Leakage, Pipes, Pressure, Pressure vessels

Proceedings Papers

The Influence of the Wall Stored Energy on the Natural-Circulation Mode in the Core Make-Up Tank Test Facility

Mingzhang Zhu, Huajian Chang, Han Wang, Xi Xu, Yang Shi

Proc. ASME. ICONE24, Volume 3: Thermal-Hydraulics, V003T09A023, June 26–30, 2016

Paper No: ICONE24-60414

DOI: https://doi.org/10.1115/ICONE24-60414

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Topics: Test facilities, Flow (Dynamics), Simulation, Thermal stratification, Engineering prototypes, Water, Density, Design, Energy budget (Physics), Heat

Proceedings Papers

Experimental Investigation on the Thermal and Flow Characteristics in the IRWST Under Spraying of the Steam From Automatic Depressurization System in AP1000 Plant

Daogang Lu, Yuhao Zhang, Zhongyi Wang, Guanghao Wu, Qiong Cao

Proc. ASME. ICONE24, Volume 3: Thermal-Hydraulics, V003T09A024, June 26–30, 2016

Paper No: ICONE24-60416

DOI: https://doi.org/10.1115/ICONE24-60416

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Topics: Flow (Dynamics), Plasma spraying, Spraying (Coating processes), Steam, Condensation, Thermal stratification, Thermocouples, Containment, Corners (Structural elements), Fluids

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NARROW

Development of Effective Momentum Model for Steam Injection Through Multi-Hole Spargers: Unit Cell Model

Numerical Analysis of Pressurized Thermal Shock in Reactor Pressure Vessel

Development of Effective Momentum Model for Steam Injection Through Multi-Hole Spargers Using a Condensation Region Approach

Experimental Investigations on Thermal Stratification in a Large Pool of Water With Immersed Isolation Condenser

Development of Evaluation Method for Thermal Stratification by Cavity Flow in a Vertical Branch Pipe With Elbow and Horizontal Section: Experimental Results

Development of Evaluation Method for Thermal Stratification by Cavity Flow in a Vertical Branch Pipe With Elbow and Horizontal Section: Modeling of Evaluation Method

Two Phase Flow Behavior During Pool Scrubbing

Thermal Stratification Modeling for Sodium-Cooled Fast Reactors: A Status Update

Validation of a Code and Effect of Turbulence Model on Predicting Thermal Stratification Phenomena in the Upper Plenum of SFR

A Validation of RELAP on Predicting Nuclear Power Plant Phenomena

Numerical Simulation for Effect of Rolling Motion on Thermal Stratification in a Surge Line

Numerical Simulation of Fluid Mixing and Stratification in Large Space

Thermal Stratification Analysis and Fatigue Evaluation for Pressurizer Surge Line in Nuclear Power Plant

Experimental Investigation on the Pipe Leakage

The Experimental Study on Stratification and Transport of Hydrogen in the Containment With Light Non-Condensable Gas

Method for Measuring Temperature of Inner Wall Surface of Pipeline in Nuclear Power Plant

The Effect of IRWST Simulation Method on the Analysis of Small Break LOCA Using RELAP5

Investigation on Accident Progression and Melt Behavior at the Fukushima Daiichi Units 1 and 2 Using MELCOR Code

The Influence of the Wall Stored Energy on the Natural-Circulation Mode in the Core Make-Up Tank Test Facility

Experimental Investigation on the Thermal and Flow Characteristics in the IRWST Under Spraying of the Steam From Automatic Depressurization System in AP1000 Plant

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