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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

Paper No: ICONE29-88852

DOI: https://doi.org/10.1115/ICONE29-88852

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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

Paper No: ICONE26-81307

DOI: https://doi.org/10.1115/ICONE26-81307

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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

Paper No: ICONE26-82596

DOI: https://doi.org/10.1115/ICONE26-82596

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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

Paper No: ICONE25-66054

DOI: https://doi.org/10.1115/ICONE25-66054

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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

Paper No: ICONE25-66875

DOI: https://doi.org/10.1115/ICONE25-66875

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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

Paper No: ICONE25-67779

DOI: https://doi.org/10.1115/ICONE25-67779

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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

Paper No: ICONE25-67921

DOI: https://doi.org/10.1115/ICONE25-67921

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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

Paper No: ICONE25-66974

DOI: https://doi.org/10.1115/ICONE25-66974

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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

Paper No: ICONE24-60043

DOI: https://doi.org/10.1115/ICONE24-60043

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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

Paper No: ICONE24-60929

DOI: https://doi.org/10.1115/ICONE24-60929

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Topics: Centrifugal pumps, Rotordynamics, Bearings, Rotors, Stiffness, Water, Pumps, Cooling systems, Damping, Displacement

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

Paper No: ICONE22-31136

DOI: https://doi.org/10.1115/ICONE22-31136

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Topics: China, Design, Alloys, Conceptual design, Coolants, Corrosion, Engineering design, Engineering prototypes, Fast neutron reactors, Fuels

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

Paper No: ICONE22-30934

DOI: https://doi.org/10.1115/ICONE22-30934

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Topics: Entropy, Junctions, Computer simulation, Energy conservation, Engineering design, Flow (Dynamics), Laminar flow, Nuclear reactors, Safety, Turbulence

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

Paper No: ICONE22-31216

DOI: https://doi.org/10.1115/ICONE22-31216

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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

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

Paper No: ICONE22-30499

DOI: https://doi.org/10.1115/ICONE22-30499

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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

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

Paper No: ICONE22-30120

DOI: https://doi.org/10.1115/ICONE22-30120

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Topics: Design, Genetic algorithms, Nuclear power, Optimization, Algorithms, Boilers, Condensers (steam plant), Engineering design, Weight (Mass)

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

Paper No: ICONE21-15397

DOI: https://doi.org/10.1115/ICONE21-15397

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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

Paper No: ICONE21-16503

DOI: https://doi.org/10.1115/ICONE21-16503

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Topics: Heat sinks, Safety, Spent nuclear fuels, Water, Cooling, Boiling, Water temperature, Fuels, Coolants, Cooling systems

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

Paper No: ICONE21-15503

DOI: https://doi.org/10.1115/ICONE21-15503

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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

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

Paper No: ICONE21-16870

DOI: https://doi.org/10.1115/ICONE21-16870

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Topics: Design, Nuclear power stations, Collaboration, Control systems, Engineering design, Instrumentation, Safety

Proceedings Papers

Structure Design of Pressure Equipment for Experimental Test on Steam Condensation on the Cold Surface

Lin Yang, Lingyun Li, Liyong Han

Proc. ASME. ICONE20-POWER2012, Volume 3: Thermal-Hydraulics; Turbines, Generators, and Auxiliaries, 309-313, July 30–August 3, 2012

Paper No: ICONE20-POWER2012-54407

DOI: https://doi.org/10.1115/ICONE20-POWER2012-54407

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Topics: Condensation, Containment, Design, Pressure, Pressure equipment, Steam, Heat, Cooling systems, Engineering design, High pressure (Physics)

NARROW

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

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

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

Design and Development of FES’s HMI for HPR1000 NPP

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

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

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

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

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

Rotor Dynamics of Multistage Centrifugal Pump

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

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

Developing Structural Design Criteria for Fusion Reactor In-Vessel Components

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

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

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

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

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

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

Structure Design of Pressure Equipment for Experimental Test on Steam Condensation on the Cold Surface

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