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Proceedings Papers

Research Methods and Protective Measures for Internal Flooding Analysis of Nuclear Islands

Guang Du, Danfeng Zhao, Daping Lin, Xiaoxia Chen
Proc. ASME. ICONE31, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A021, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-135047
https://doi.org/10.1115/ICONE31-135047
View Paper titled, Research Methods and Protective Measures for Internal Flooding Analysis of Nuclear Islands
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Topics: Floods, Nuclear power stations, Design, Hazards, Safety, Water, Computational methods, Engineering design, Evaluation methods, Nuclear power
Proceedings Papers

Scaling and Engineering Design of Facility for Simulation of HTGR Reactor Building Response for a Break in Primary Coolant Break

Shripad T. Revankar, Derek W. Kultgen
Proc. ASME. ICONE29, Volume 7A: Thermal-Hydraulics and Safety Analysis, V07AT07A004, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-88852
https://doi.org/10.1115/ICONE29-88852
View Paper titled, Scaling and Engineering Design of Facility for Simulation of HTGR Reactor Building Response for a Break in Primary Coolant Break
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Topics: Accidents, Coolants, Design, Engineering design, Simulation, Test facilities, Very high temperature reactors
Proceedings Papers

Post-Test CFD Analysis of Non-Uniformly Heated 19-Pin Fuel Bundle Cooled by HLM

R. Marinari, I. Di Piazza, M. Angelucci, D. Martelli
Proc. ASME. ICONE26, Volume 8: Computational Fluid Dynamics (CFD); Nuclear Education and Public Acceptance, V008T09A008, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81307
https://doi.org/10.1115/ICONE26-81307
View Paper titled, Post-Test CFD Analysis of Non-Uniformly Heated 19-Pin Fuel Bundle Cooled by HLM
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Topics: Computational fluid dynamics, Fuels, Mixed convection, Coolants, Density, Electrical conductivity, Engineering design, Engineering prototypes, Errors, Fast neutron reactors
Proceedings Papers

Stress and Fatigue Analysis of Thermal Shock for Cladding of Center Measurement Column Lower Head in the Fast Reactor Under Shutdown Condition

Shu Zheng, Daogang Lu, Qiong Cao, Chao Liu, Yunlong Ding, Yi Huang
Proc. ASME. ICONE26, Volume 6B: Thermal-Hydraulics and Safety Analyses, V06BT08A069, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-82596
https://doi.org/10.1115/ICONE26-82596
View Paper titled, Stress and Fatigue Analysis of Thermal Shock for Cladding of Center Measurement Column Lower Head in the Fast Reactor Under Shutdown Condition
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Topics: Cladding systems (Building), Fast neutron reactors, Fatigue analysis, Stress, Thermal shock, Fatigue damage, Temperature, Coolants, Damage, Design
Proceedings Papers

Design and Development of FES’s HMI for HPR1000 NPP

Caike Zhang, Peibang Liu, Hanjun Gao, Chenglong Xie, Ming Qu
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, V001T04A003, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-66054
https://doi.org/10.1115/ICONE25-66054
View Paper titled, Design and Development of FES’s HMI for HPR1000 NPP
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Topics: Design, Nuclear power stations, Computer software, Simulation, Errors, Machinery, Cycles, Feedback, Computers, Data acquisition
Proceedings Papers

Nonlinear Analysis Method Research of Multi-Bolt Connection Structure of Primary Equipment Support

Jianrong Zou, Shaochong Zhou
Proc. ASME. ICONE25, Volume 2: Plant Systems, Structures, Components and Materials, V002T03A069, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-66875
https://doi.org/10.1115/ICONE25-66875
View Paper titled, Nonlinear Analysis Method Research of Multi-Bolt Connection Structure of Primary Equipment Support
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Topics: ASME Standards, Boilers, Computational methods, Design, Engineering design, Finite element methods, Flange connections, Flanges, Girders, Junctions
Proceedings Papers

Simulation of Behaviors of a One-Third Scale Containment Model Test

Guopeng Ren, Rong Pan, Feng Sun
Proc. ASME. ICONE25, Volume 2: Plant Systems, Structures, Components and Materials, V002T03A113, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-67779
https://doi.org/10.1115/ICONE25-67779
View Paper titled, Simulation of Behaviors of a One-Third Scale Containment Model Test
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Topics: Containment, Simulation, Tendons, Concretes, Finite element model, Pressure, Deformation, Nuclear power stations, Design, Safety
Proceedings Papers

Enhanced Heat Transfer Structure Design for Ion Dump of EAST-NBI System Based on Hypervapotron

Ling Tao, Chundong Hu, Yuanlai Xie
Proc. ASME. ICONE25, Volume 2: Plant Systems, Structures, Components and Materials, V002T03A115, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-67921
https://doi.org/10.1115/ICONE25-67921
View Paper titled, Enhanced Heat Transfer Structure Design for Ion Dump of EAST-NBI System Based on Hypervapotron
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Topics: Design, Heat transfer, Heat, Particulate matter, Boiling, Deflection, Engineering design, Fluids, Magnets, Neutral beams
Proceedings Papers

Methodology and Application of Human Reliability Analysis in CAP1400 Nuclear Power Plant

Yongping Qiu, Jiandong He, Juntao Hu, Yucheng Zhuo, Jie He
Proc. ASME. ICONE25, Volume 4: Nuclear Safety, Security, Non-Proliferation and Cyber Security; Risk Management, V004T14A029, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-66974
https://doi.org/10.1115/ICONE25-66974
View Paper titled, Methodology and Application of Human Reliability Analysis in CAP1400 Nuclear Power Plant
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Topics: Human reliability analysis, Nuclear power stations, Human factors, Safety, Engineering design, Failure, Fire, Floods, Probabilistic safety assessment
Proceedings Papers

The Application of PSHA Method in the Determination of Beyond Design Basis Earthquake for New NPP Design

Ziduan Shang, Xiao Huang, Meng Chu, Lutong Zhang, Chunhua Wu
Proc. ASME. ICONE24, Volume 1: Operations and Maintenance, Aging Management and Plant Upgrades; Nuclear Fuel, Fuel Cycle, Reactor Physics and Transport Theory; Plant Systems, Structures, Components and Materials; I&C, Digital Controls, and Influence of Human Factors, V001T03A002, June 26–30, 2016
Publisher: American Society of Mechanical Engineers
Paper No: ICONE24-60043
https://doi.org/10.1115/ICONE24-60043
View Paper titled, The Application of PSHA Method in the Determination of Beyond Design Basis Earthquake for New NPP Design
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Topics: Design, Earthquakes, Nuclear power stations, Economics , Engineering design, Engineering design processes, Modeling, Nuclear engineering, Regulations, Safety
Proceedings Papers

Rotor Dynamics of Multistage Centrifugal Pump

Hua He, Bo Zhang, Guo-pei Pan, Gang Zhao
Proc. ASME. ICONE24, Volume 5: Student Paper Competition, V005T15A070, June 26–30, 2016
Publisher: American Society of Mechanical Engineers
Paper No: ICONE24-60929
https://doi.org/10.1115/ICONE24-60929
View Paper titled, Rotor Dynamics of Multistage Centrifugal Pump
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Topics: Centrifugal pumps, Rotordynamics, Bearings, Rotors, Stiffness, Water, Pumps, Cooling systems, Damping, Displacement
Proceedings Papers

Application of Dual-Adaptive Niched Genetic Algorithm in Optimal Design of Nuclear Power Components

Cheng Wang, Chang-qi Yan, Jian-jun Wang, Lei Chen, Gui-jing Li
Proc. ASME. ICONE22, Volume 2A: Thermal Hydraulics, V02AT09A013, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-30120
https://doi.org/10.1115/ICONE22-30120
View Paper titled, Application of Dual-Adaptive Niched Genetic Algorithm in Optimal Design of Nuclear Power Components
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Topics: Design, Genetic algorithms, Nuclear power, Optimization, Algorithms, Boilers, Condensers (steam plant), Engineering design, Weight (Mass)
Proceedings Papers

Developing Structural Design Criteria for Fusion Reactor In-Vessel Components

M. Kalsey, M. Porton
Proc. ASME. ICONE22, Volume 6: Nuclear Education, Public Acceptance and Related Issues; Instrumentation and Controls (I&C); Fusion Engineering; Beyond Design Basis Events, V006T14A008, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-31216
https://doi.org/10.1115/ICONE22-31216
View Paper titled, Developing Structural Design Criteria for Fusion Reactor In-Vessel Components
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Topics: Fusion reactors, Structural design, Vessels, Design, Conceptual design, Construction, Engineering design, Human factors, Power stations, Structural elements (Construction)
Proceedings Papers

Estimation of Loss Coefficient for T-Junction by an Entropy Production Approach

Y. Ji, H.-C. Zhang, Yi.-N. Zhang, Y. Li, L.-M. Yan
Proc. ASME. ICONE22, Volume 2B: Thermal Hydraulics, V02BT09A036, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-30934
https://doi.org/10.1115/ICONE22-30934
View Paper titled, Estimation of Loss Coefficient for T-Junction by an Entropy Production Approach
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Topics: Entropy, Junctions, Computer simulation, Energy conservation, Engineering design, Flow (Dynamics), Laminar flow, Nuclear reactors, Safety, Turbulence
Proceedings Papers

Retrieving Fuel Elements by Pneumatic Suction in Pebble-Bed High Temperature Gas-Cooled Reactor

Bin Wu, Jin-hua Wang, Yue Li, Bing Wang, Ji-guo Liu
Proc. ASME. ICONE22, Volume 1: Plant Operations, Maintenance, Engineering, Modifications, Life Cycle and Balance of Plant; Nuclear Fuel and Materials; Plant Systems, Structures and Components; Codes, Standards, Licensing and Regulatory Issues, V001T02A010, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-30499
https://doi.org/10.1115/ICONE22-30499
View Paper titled, Retrieving Fuel Elements by Pneumatic Suction in Pebble-Bed High Temperature Gas-Cooled Reactor
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Topics: Fuels, Suction, Very high temperature reactors, Pressure, Damage, Pressure drop, Spent fuel storage, Air flow, Design, Dynamics (Mechanics)
Proceedings Papers

Design and R&D Progress of China Lead-Based Reactor

Yican Wu, Yunqing Bai, Yong Song, Qunying Huang, Zhumin Zhao, Gang Song, Liqin Hu, Jieqiong Jiang
Proc. ASME. ICONE22, Volume 3: Next Generation Reactors and Advanced Reactors; Nuclear Safety and Security, V003T06A051, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-31136
https://doi.org/10.1115/ICONE22-31136
View Paper titled, Design and R&D Progress of China Lead-Based Reactor
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Topics: China, Design, Alloys, Conceptual design, Coolants, Corrosion, Engineering design, Engineering prototypes, Fast neutron reactors, Fuels
Proceedings Papers

Overview on the Design Approach for the CVCS I & C of the EPR™ Nuclear Power Plant in Taishan

Antonio Ciriello, Daniela Kohler, Terry Morton, Thomas Lang
Proc. ASME. ICONE21, Volume 2: Plant Systems, Construction, Structures and Components; Next Generation Reactors and Advanced Reactors, V002T05A074, July 29–August 2, 2013
Publisher: American Society of Mechanical Engineers
Paper No: ICONE21-16870
https://doi.org/10.1115/ICONE21-16870
View Paper titled, Overview on the Design Approach for the CVCS I & C of the EPR™ Nuclear Power Plant in Taishan
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Topics: Design, Nuclear power stations, Collaboration, Control systems, Engineering design, Instrumentation, Safety
Proceedings Papers

Research on the Stainless Steel Tubes and Pipes Material Standards of Demonstration Fast Reactor Power Plant

Yaping Li, Guangdong Song
Proc. ASME. ICONE21, Volume 2: Plant Systems, Construction, Structures and Components; Next Generation Reactors and Advanced Reactors, V002T05A011, July 29–August 2, 2013
Publisher: American Society of Mechanical Engineers
Paper No: ICONE21-15503
https://doi.org/10.1115/ICONE21-15503
View Paper titled, Research on the Stainless Steel Tubes and Pipes Material Standards of Demonstration Fast Reactor Power Plant
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Topics: Fast neutron reactors, Pipes, Power stations, Stainless steel, Construction, High temperature, Sodium, Engineering design, High pressure (Physics), Liquid metals
Proceedings Papers

Investigation on Multi-Objective Optimal Design of a Two Pass Condenser

Lei Chen, Chang-qi Yan, Jian-jun Wang
Proc. ASME. ICONE21, Volume 4: Thermal Hydraulics, V004T09A035, July 29–August 2, 2013
Publisher: American Society of Mechanical Engineers
Paper No: ICONE21-15397
https://doi.org/10.1115/ICONE21-15397
View Paper titled, Investigation on Multi-Objective Optimal Design of a Two Pass Condenser
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Topics: Condensers (steam plant), Design, Coolants, Weight (Mass), Flow (Dynamics), Algorithms, Dimensions, Engineering design, Genetic algorithms, Nuclear power stations
Proceedings Papers

Safety Analysis of CPR1000 Spent Fuel Pool in Case of Loss of Heat Sink

Haitao Wang, Li Ge, Jianqiang Shan, Junli Gou, Bo Zhang
Proc. ASME. ICONE21, Volume 4: Thermal Hydraulics, V004T09A096, July 29–August 2, 2013
Publisher: American Society of Mechanical Engineers
Paper No: ICONE21-16503
https://doi.org/10.1115/ICONE21-16503
View Paper titled, Safety Analysis of CPR1000 Spent Fuel Pool in Case of Loss of Heat Sink
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Topics: Heat sinks, Safety, Spent nuclear fuels, Water, Cooling, Boiling, Water temperature, Fuels, Coolants, Cooling systems