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Proceedings Papers

Analysis on the Leakage Behavior of Cable Facility Using Gothic and Gothic 3D Models

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Ningxi Jia, Zhuo Liu, Yidan Yuan
Proc. ASME. ICONE31, Volume 6: Thermal-Hydraulics and Safety Analysis, V006T07A004, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-130093
https://doi.org/10.1115/ICONE31-130093
View Paper titled, Analysis on the Leakage Behavior of Cable Facility Using Gothic and Gothic 3D Models
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Topics: Cables, Distributed parameter models, Leakage, Lumped parameter models, Three-dimensional models
Proceedings Papers

Analysis of EBR-II Loss-of-Flow Transients With 3D Model of CATHARE Code

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Xiaolin Chen, Simon Li, Songbai Cheng
Proc. ASME. ICONE29, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A025, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92109
https://doi.org/10.1115/ICONE29-92109
View Paper titled, Analysis of EBR-II Loss-of-Flow Transients With 3D Model of CATHARE Code
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Topics: Accidents, Flow (Dynamics), Sodium fast reactors, Three-dimensional models, Transients (Dynamics)
Proceedings Papers

Numerical Simulation Analysis of the Air Temperature Measurement Scheme for Big Space in Containment

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Tiexin Fan, Xianbin Zeng, Qi Niu, Bin Tu, Dongshan Huang, Zhengjie Liu
Proc. ASME. ICONE29, Volume 8: Computational Fluid Dynamics (CFD) and Applications, V008T08A065, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-93513
https://doi.org/10.1115/ICONE29-93513
View Paper titled, Numerical Simulation Analysis of the Air Temperature Measurement Scheme for Big Space in Containment
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Topics: Computational fluid dynamics, Computer simulation, Containment, Design, Temperature measurement, Temperature, Computer software, Computer-aided design, Nuclear power stations, Accidents
Proceedings Papers

Development and Application of Modular Information Management System for Nuclear Power Engineering

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Xiaocheng Gong, Xinwei Xu, Wei Zhou
Proc. ASME. ICONE29, Volume 12: Innovative and Smart Nuclear Power Plant Design, V012T12A016, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92073
https://doi.org/10.1115/ICONE29-92073
View Paper titled, Development and Application of Modular Information Management System for Nuclear Power Engineering
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Topics: Design, Nuclear engineering, Construction, Nuclear power, Modular construction, China, Domes (Structural elements), Linings (Textiles), Nuclear power stations, Steel
Proceedings Papers

Research and Development of Three-Dimensional Digital Operation Management Platform for NPPs

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Hao Wang, Li-Cheng Tian, Jia Lin, Hui-Zhen Huang
Proc. ASME. ICONE29, Volume 12: Innovative and Smart Nuclear Power Plant Design, V012T12A032, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92994
https://doi.org/10.1115/ICONE29-92994
View Paper titled, Research and Development of Three-Dimensional Digital Operation Management Platform for NPPs
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Topics: Cycles, Industrial research, Maintenance, Nuclear power stations, Three-dimensional models, Nuclear power, Design, Inspection, Visualization
Proceedings Papers

Application of Combining 3D Model and Survey on Site to Simulate Dome Lifting

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Wei-ting He, Yuan-xia Zhou, Jie Yang
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, V001T02A033, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-65502
https://doi.org/10.1115/ICONE28-65502
View Paper titled, Application of Combining 3D Model and Survey on Site to Simulate Dome Lifting
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Topics: Domes (Structural elements), Plasma desorption mass spectrometry, Three-dimensional models
Proceedings Papers

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

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R. Lo Frano, S. Paci, P. Darnowski, P. Mazgaj
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, V001T01A016, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16664
https://doi.org/10.1115/ICONE2020-16664
View Paper titled, Study of the Ageing Effects on the Lower Head Failure in a PWR Reactor
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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

Evaluations of TiO 2 Deposition on Structure Surfaces and Water Radiolysis for the Corrosive Environment in a Reactor Pressure Vessel

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Takashi Mawatari, Yasushi Yamamoto, Osamu Shibasaki, Takahiro Hara, Yusuke Horayama, Junichi Takagi
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, V001T06A013, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16405
https://doi.org/10.1115/ICONE2020-16405
View Paper titled, Evaluations of TiO 2 Deposition on Structure Surfaces and Water Radiolysis for the Corrosive Environment in a Reactor Pressure Vessel
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Topics: Reactor vessels, Stress corrosion cracking, Titanium dioxide, Water, Flow (Dynamics), Computational fluid dynamics, Resolution (Optics), Risk, Boiling water reactors, Catalysts
Proceedings Papers

Strength Limit of Thimble Tube With Material Plasticity Under Bending Moment and Axial Compression Force

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Hisashi Koike, Masaji Mori, Daisuke Fujiwara, Takashi Shimomura
Proc. ASME. ICONE26, Volume 3: Nuclear Fuel and Material, Reactor Physics, and Transport Theory, V003T02A020, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81468
https://doi.org/10.1115/ICONE26-81468
View Paper titled, Strength Limit of Thimble Tube With Material Plasticity Under Bending Moment and Axial Compression Force
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Topics: ASME Standards, Compression, Earthquakes, Evaluation methods, Fuels, Manufacturing, Plasticity, Plastics, Pressurized water reactors, Stress
Proceedings Papers

CFD Numerical Simulation of Water Hammer in a Vortex Diode

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Junrong Wang, Zhiguo Wei, Jinlan Gou, Qi Xiao, Shaodan Li, Yong Li
Proc. ASME. ICONE26, Volume 8: Computational Fluid Dynamics (CFD); Nuclear Education and Public Acceptance, V008T09A027, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81790
https://doi.org/10.1115/ICONE26-81790
View Paper titled, CFD Numerical Simulation of Water Hammer in a Vortex Diode
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Topics: Computational fluid dynamics, Computer simulation, Vortices, Water hammer, Pipeline systems, Valves, Pressure, Pumps, Leakage, Nuclear industry
Proceedings Papers

CFD Validation With a PIV Provided Experimental Data for the Coolant Velocity Measurement in Reactor Vessel Down-Comer

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Abdelgadir Eltayeb, Sichao Tan, Ayodeji A. Ala, Zhang Qi, Nisrene M. Ahmed
Proc. ASME. ICONE26, Volume 4: Nuclear Safety, Security, and Cyber Security; Computer Code Verification and Validation, V004T15A016, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-82212
https://doi.org/10.1115/ICONE26-82212
View Paper titled, CFD Validation With a PIV Provided Experimental Data for the Coolant Velocity Measurement in Reactor Vessel Down-Comer
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Topics: Computational fluid dynamics, Coolants, Reactor vessels, Velocity measurement, Fluid dynamics, Pressurized water reactors, Boundary-value problems, Cylinders, Engineering simulation, Flow (Dynamics)
Proceedings Papers

The Design of a Nuclear Emergency Decision Deduction and Training Platform

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Li Ke, Liang Manchun, Su Guofeng, Yang Jie, He Jingtao, He Shuijun
Proc. ASME. ICONE26, Volume 4: Nuclear Safety, Security, and Cyber Security; Computer Code Verification and Validation, V004T06A022, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81691
https://doi.org/10.1115/ICONE26-81691
View Paper titled, The Design of a Nuclear Emergency Decision Deduction and Training Platform
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Topics: Design, Emergencies, Simulation, Accidents, Emergency preparedness, Nuclear power stations, Security, China, Computer simulation, Computer software
Proceedings Papers

Research on Heat Transfer Characteristics of the Thermometric Sphere in HTR-10

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Shiyan Sun, Youjie Zhang, Yanhua Zheng, Xiang Fang, Xiaoyong Yang
Proc. ASME. ICONE26, Volume 5: Advanced Reactors and Fusion Technologies; Codes, Standards, Licensing, and Regulatory Issues, V005T05A015, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81768
https://doi.org/10.1115/ICONE26-81768
View Paper titled, Research on Heat Transfer Characteristics of the Thermometric Sphere in HTR-10
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Topics: Heat transfer, Temperature, Graphite, Metals, Thermal equilibrium, Very high temperature reactors, Wire, Computational fluid dynamics, Construction, Convection
Proceedings Papers

The Numerical Simulation Research of Gas Entrainment Based on Three-Dimensional Model

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Yilin Zhang, Shanfang Huang
Proc. ASME. ICONE25, Volume 8: Computational Fluid Dynamics (CFD) and Coupled Codes; Nuclear Education, Public Acceptance and Related Issues, V008T09A025, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-66725
https://doi.org/10.1115/ICONE25-66725
View Paper titled, The Numerical Simulation Research of Gas Entrainment Based on Three-Dimensional Model
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Topics: Computer simulation, Three-dimensional models, Flow (Dynamics), Porosity, Simulation results, Coolants, External pressure, Fluid density, Fluids, Fracture (Materials)
Proceedings Papers

Numerical Simulation of Flow Distribution in the Lower Plenum of NHR200-II

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Wei Li, Dingqu Wang, Yueyuan Jiang, Songyang Li, Wenli Guo, Wei Xiong, Weihua Li, Heng Xie, Xiaotian Li
Proc. ASME. ICONE25, Volume 8: Computational Fluid Dynamics (CFD) and Coupled Codes; Nuclear Education, Public Acceptance and Related Issues, V008T09A051, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-67746
https://doi.org/10.1115/ICONE25-67746
View Paper titled, Numerical Simulation of Flow Distribution in the Lower Plenum of NHR200-II
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Topics: Computer simulation, Flow (Dynamics), Vortices, Pressure, Coolants, Design, Heat, Heating, Pressurized water reactors, Reactor vessels
Proceedings Papers

Flow Field Analysis of the Reactor Coolant Pump Internal Cooling Circulation

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Jie Qin, Qingmu Xu, Junkai Yuan, Kun Cai
Proc. ASME. ICONE25, Volume 8: Computational Fluid Dynamics (CFD) and Coupled Codes; Nuclear Education, Public Acceptance and Related Issues, V008T09A040, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-67179
https://doi.org/10.1115/ICONE25-67179
View Paper titled, Flow Field Analysis of the Reactor Coolant Pump Internal Cooling Circulation
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Topics: Cooling, Flow (Dynamics), Nuclear reactor coolants, Pumps, Bearings, Engines, Motors, Flywheels, Heat, Heat transfer
Proceedings Papers

Analysis of the Containment Thermal-Hydraulic Behavior of a Small Reactor During Loss of Coolant Accident

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Qian Lin, Weizhong Zhang
Proc. ASME. ICONE25, Volume 6: Thermal-Hydraulics, V006T08A026, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-66318
https://doi.org/10.1115/ICONE25-66318
View Paper titled, Analysis of the Containment Thermal-Hydraulic Behavior of a Small Reactor During Loss of Coolant Accident
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Topics: Accidents, Containment, Coolants, Condensers (steam plant), Three-dimensional models, Cooling systems, Economics , Heat, Heat exchangers, Pressure
Proceedings Papers

Numerical Investigation of Melt Jet Breakup With Different Shapes in Water Pool

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Hui Cheng, Jiyun Zhao
Proc. ASME. ICONE25, Volume 6: Thermal-Hydraulics, V006T08A103, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-67611
https://doi.org/10.1115/ICONE25-67611
View Paper titled, Numerical Investigation of Melt Jet Breakup With Different Shapes in Water Pool
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Topics: Shapes, Water, Fuels, Three-dimensional models, Explosions, Steam, Accidents, Coolants, Damage, Deformation
Proceedings Papers

The Research on Ultrasonic Testing Technology for Bottom Part of Reactor Pressure Vessel

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Ge Liang, Xu Xuguang, Cai Jiafan, Cheng Zhaoyu
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, V001T01A027, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-66984
https://doi.org/10.1115/ICONE25-66984
View Paper titled, The Research on Ultrasonic Testing Technology for Bottom Part of Reactor Pressure Vessel
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Topics: Reactor vessels, Ultrasonic testing, Probes, Inspection, Alloys, Nuclear power stations, Accuracy and precision, Circuits, Corrosion, Design
Proceedings Papers

Application of GOTHIC8.0 3D Model to Simulate Heat Removal Process in Containment Safety Verification via Integral Test (CERT)

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Guodong Wang, Shengjie Wei, Chenxiao Ni, Di Zhang, Zhe Wang
Proc. ASME. ICONE25, Volume 6: Thermal-Hydraulics, V006T08A100, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-67560
https://doi.org/10.1115/ICONE25-67560
View Paper titled, Application of GOTHIC8.0 3D Model to Simulate Heat Removal Process in Containment Safety Verification via Integral Test (CERT)
Open the PDF for Application of GOTHIC8.0 3D Model to Simulate Heat Removal Process in Containment Safety Verification via Integral Test (CERT) in another window
Topics: Containment, Heat, Safety, Three-dimensional models, Shells, Steam, Vessels, Condensation, Evaporation, Water