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Proceedings Papers

Numerical Simulation of Added Mass in Narrow Gaps of Multi-Layer Thin-Walled Shell of Fast Reactor

Dexuan Duan, Daogang Lu, Yu Liu, Donghao Li

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, V003T08A009, August 4–6, 2021

Paper No: ICONE28-64644

DOI: https://doi.org/10.1115/ICONE28-64644

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Topics: Computer simulation, Fast neutron reactors, Finite element analysis, Fluid structure interaction, Shells

Proceedings Papers

Three-Dimensional Numerical Simulation on Transient Natural Circulation Characteristics of DRACS in PLANDTL-DHX Experimental Device

Zijia Chen, Daogang Lu, Jinsong Guo, Yuhao Zhang

Paper No: ICONE28-64515

DOI: https://doi.org/10.1115/ICONE28-64515

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Topics: Computer simulation, Sodium fast reactors, Transients (Dynamics)

Proceedings Papers

Dropping-Rod Analysis of Control Rod in ADS Lead-Bismuth Alloy Zero-Power Reactor

Hui Fu, Daogang Lu, Yu Liu

Paper No: ICONE28-64082

DOI: https://doi.org/10.1115/ICONE28-64082

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Topics: Alloys, Safety, Earthquakes, Collisions (Physics), Computer simulation, Coolants, Finite element methods, Leakage, Neutrons, Nuclear fuels

Proceedings Papers

Stress Analysis of the Lower Head of Central Measuring Shroud Under Thermal Striping and Thermal Shock Conditions

Shu Zheng, Daogang Lu, Qiong Cao

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, V001T06A019, August 4–5, 2020

Paper No: ICONE2020-16668

DOI: https://doi.org/10.1115/ICONE2020-16668

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Topics: Fatigue analysis, Stress analysis (Engineering), Thermal shock

Proceedings Papers

Experimental and Numerical Research on Steam Direct Contact Condensation Process in Automatic Depressurization System of AP1000

Yuhao Zhang, Li Feng, Zhimin Qiu, Jingpin Fu, Daogang Lu

Proc. ASME. ICONE2020, Volume 3: Student Paper Competition; Thermal-Hydraulics; Verification and Validation, V003T13A044, August 4–5, 2020

Paper No: ICONE2020-16780

DOI: https://doi.org/10.1115/ICONE2020-16780

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Topics: Condensation, Steam

Proceedings Papers

Code to Code Validation of SAC-3D Based on EBR-II Benchmark Problem

Daogang Lu, Siyu Lyu, Danting Sui

Proc. ASME. ICONE2020, Volume 3: Student Paper Competition; Thermal-Hydraulics; Verification and Validation, V003T14A006, August 4–5, 2020

Paper No: ICONE2020-16666

DOI: https://doi.org/10.1115/ICONE2020-16666

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Topics: Accidents, Carbon reinforced plastics, China, Electricity (Physics), Fast neutron reactors, Feedback, Flow (Dynamics), Nuclear reactors, Safety, Scram

Proceedings Papers

Influence of Gap Size on Added Mass for Spent Fuel Storage Rack

Daogang Lu, Yu Liu, Shu Zheng

Proc. ASME. ICONE26, Volume 2: Plant Systems, Structures, Components, and Materials; Risk Assessments and Management, V002T03A033, July 22–26, 2018

Paper No: ICONE26-82595

DOI: https://doi.org/10.1115/ICONE26-82595

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Topics: Spent fuel storage, Water, Spent nuclear fuels, Construction, Earthquakes, Fluid structure interaction, Fluids, Oscillating frequencies, Computational fluid dynamics, Design

Proceedings Papers

Experimental Comparison on the Multi-Hole Steam Spraying Condensation Heat Transfer Characteristics

Yuhao Zhang, Daogang Lu, Bin Ouyang, Yonglong Yuan

Proc. ASME. ICONE26, Volume 6B: Thermal-Hydraulics and Safety Analyses, V06BT08A064, July 22–26, 2018

Paper No: ICONE26-82518

DOI: https://doi.org/10.1115/ICONE26-82518

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Topics: Condensation, Heat transfer, Plasma spraying, Spraying (Coating processes), Steam, Flow (Dynamics), High pressure (Physics), High temperature, Oscillations, Pressurized water 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

Study on Pool Boiling Behavior of the Spent Fuel Under Accident Conditions

Shang Gao, Daogang Lu, Han Wang, Yuhang Zhong

Proc. ASME. ICONE25, Volume 9: Student Paper Competition, V009T15A017, July 2–6, 2017

Paper No: ICONE25-66616

DOI: https://doi.org/10.1115/ICONE25-66616

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Topics: Accidents, Pool boiling, Spent nuclear fuels, Temperature, Cooling, Fuels, Heat transfer coefficients, Water temperature, Heat, Heating

Proceedings Papers

Experimental Study of the Sodium-Cooled Fast Reactor Vessel Seismic Analysis Considered the Liquid Sloshing

Hongda Liu, Daogang Lu, Xiaoxuan Li, Xiaojia Zeng, Guangdong Bao

Proc. ASME. ICONE25, Volume 5: Advanced and Next Generation Reactors, Fusion Technology; Codes, Standards, Conformity Assessment, Licensing, and Regulatory Issues, V005T05A005, July 2–6, 2017

Paper No: ICONE25-66111

DOI: https://doi.org/10.1115/ICONE25-66111

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Topics: Seismic analysis, Sloshing, Sodium fast reactors, Vessels, Water, Waves, Fast neutron reactors, Pressure, Design, Earthquake resistant design

Proceedings Papers

The Application of Heat Pipe Discharge Containment Heat Experimental Study: New Type of Passive Containment Heat Removal System Concept Design

Haiqi Qin, Daogang Lu, Shengfei Wang

Proc. ASME. ICONE25, Volume 6: Thermal-Hydraulics, V006T08A082, July 2–6, 2017

Paper No: ICONE25-67134

DOI: https://doi.org/10.1115/ICONE25-67134

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Topics: Containment, Design, Heat, Heat pipes, Accidents, Conceptual design, Nuclear power, Cooling, Experimental design, Heat transfer

Proceedings Papers

Supercritical CO2 Power Cycle for Small Modular Reactor

Zhangpeng Guo, Yang Zhao, Fenglei Niu, Daogang Lu

Proc. ASME. ICONE25, Volume 6: Thermal-Hydraulics, V006T08A005, July 2–6, 2017

Paper No: ICONE25-66103

DOI: https://doi.org/10.1115/ICONE25-66103

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Topics: Small modular reactors, Supercritical carbon dioxide, Thermodynamic power cycles, Turbines, Cycles, Pressure, Temperature, Thermal efficiency, Nuclear power stations, Steam

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

Proceedings Papers

Development and Application of the Neutronics/Thermal-Hydraulics Coupling Code for Safety Analysis of EBR-II Loss of Heat Sink Tests Without Scram

Daogang Lu, Chao Guo, Danting Sui

Proc. ASME. ICONE24, Volume 4: Computational Fluid Dynamics (CFD) and Coupled Codes; Decontamination and Decommissioning, Radiation Protection, Shielding, and Waste Management; Workforce Development, Nuclear Education and Public Acceptance; Mitigation Strategies for Beyond Design Basis Events; Risk Management, V004T10A025, June 26–30, 2016

Paper No: ICONE24-60862

DOI: https://doi.org/10.1115/ICONE24-60862

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Topics: Heat sinks, Safety, Scram, Thermal hydraulics, Liquid metal fast breeder reactors, Sodium fast reactors, Transients (Dynamics), Breeder reactors, Fast neutron reactors, Feedback

Proceedings Papers

Preliminary Development of System Analysis Code for Traveling-Wave Reactor

Chao Guo, Daogang Lu, Hao Huang

Proc. ASME. ICONE21, Volume 2: Plant Systems, Construction, Structures and Components; Next Generation Reactors and Advanced Reactors, V002T05A017, July 29–August 2, 2013

Paper No: ICONE21-15737

DOI: https://doi.org/10.1115/ICONE21-15737

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Topics: Systems analysis, Traveling waves, Fuels, Uranium, Light water reactors, Nuclear reactors, Safety, Centrifugal pumps, China, Design

Proceedings Papers

A Conceptual Design of a Small Modular Natural-Circulation Liquid Metal Fast Reactor With AMTEC Units

Xun Zhang, Daogang Lu

Proc. ASME. ICONE21, Volume 2: Plant Systems, Construction, Structures and Components; Next Generation Reactors and Advanced Reactors, V002T05A006, July 29–August 2, 2013

Paper No: ICONE21-15235

DOI: https://doi.org/10.1115/ICONE21-15235

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Topics: Conceptual design, Liquid metal cooled reactors, Design, Heat, Power conversion systems, Alkali metals, Construction, Distributed power generation, Energy conversion, Heat exchangers

Proceedings Papers

CFD Analysis of Thermal Stratification Phenomena in the RNS Suction Line of a Gen-III Nuclear Power Plant

Yan Li, Daogang Lu, Zhigang Wang, Jian Wu, Fengyun Yu

Proc. ASME. ICONE21, Volume 3: Nuclear Safety and Security; Codes, Standards, Licensing and Regulatory Issues; Computational Fluid Dynamics and Coupled Codes, V003T10A025, July 29–August 2, 2013

Paper No: ICONE21-15735

DOI: https://doi.org/10.1115/ICONE21-15735

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Topics: Computational fluid dynamics, Nuclear power stations, Suction, Thermal stratification, Leakage, Temperature, Flow (Dynamics), Pipes, Density, Heat

Proceedings Papers

The Research of the Fluid-Solid Interaction of the Passive Containment Cooling Tank and Shield Building Structure With Seismic Load in AP1000

Junjie Dang, Daogang Lu, Wenhui Ma, Yu Liu, Yang Hong

Proc. ASME. ICONE21, Volume 3: Nuclear Safety and Security; Codes, Standards, Licensing and Regulatory Issues; Computational Fluid Dynamics and Coupled Codes, V003T10A026, July 29–August 2, 2013

Paper No: ICONE21-15778

DOI: https://doi.org/10.1115/ICONE21-15778

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Topics: Containment, Cooling, Cooling systems, Fluids, Stress

Proceedings Papers

Thermal Hydraulics Numerical Simulation and Optimized Design of Passive Residual Heat Removal Heat Exchanger in AP1000

Huining Xia, Daogang Lu, Zheng Du, Yuhao Zhang, Xiaoliang Fu, Zhongying Ma, Yanhua Yang, Min Liang

Proc. ASME. ICONE21, Volume 3: Nuclear Safety and Security; Codes, Standards, Licensing and Regulatory Issues; Computational Fluid Dynamics and Coupled Codes, V003T10A017, July 29–August 2, 2013

Paper No: ICONE21-15480

DOI: https://doi.org/10.1115/ICONE21-15480

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Topics: Computer simulation, Design, Heat, Heat exchangers, Thermal hydraulics, Heat transfer, Temperature, Fluids, Boiling, Containment

Journal citation

NARROW

Numerical Simulation of Added Mass in Narrow Gaps of Multi-Layer Thin-Walled Shell of Fast Reactor

Three-Dimensional Numerical Simulation on Transient Natural Circulation Characteristics of DRACS in PLANDTL-DHX Experimental Device

Dropping-Rod Analysis of Control Rod in ADS Lead-Bismuth Alloy Zero-Power Reactor

Stress Analysis of the Lower Head of Central Measuring Shroud Under Thermal Striping and Thermal Shock Conditions

Experimental and Numerical Research on Steam Direct Contact Condensation Process in Automatic Depressurization System of AP1000

Code to Code Validation of SAC-3D Based on EBR-II Benchmark Problem

Influence of Gap Size on Added Mass for Spent Fuel Storage Rack

Experimental Comparison on the Multi-Hole Steam Spraying Condensation Heat Transfer Characteristics

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

Study on Pool Boiling Behavior of the Spent Fuel Under Accident Conditions

Experimental Study of the Sodium-Cooled Fast Reactor Vessel Seismic Analysis Considered the Liquid Sloshing

The Application of Heat Pipe Discharge Containment Heat Experimental Study: New Type of Passive Containment Heat Removal System Concept Design

Supercritical CO2 Power Cycle for Small Modular Reactor

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

Development and Application of the Neutronics/Thermal-Hydraulics Coupling Code for Safety Analysis of EBR-II Loss of Heat Sink Tests Without Scram

Preliminary Development of System Analysis Code for Traveling-Wave Reactor

A Conceptual Design of a Small Modular Natural-Circulation Liquid Metal Fast Reactor With AMTEC Units

CFD Analysis of Thermal Stratification Phenomena in the RNS Suction Line of a Gen-III Nuclear Power Plant

The Research of the Fluid-Solid Interaction of the Passive Containment Cooling Tank and Shield Building Structure With Seismic Load in AP1000

Thermal Hydraulics Numerical Simulation and Optimized Design of Passive Residual Heat Removal Heat Exchanger in AP1000

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