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Proceedings Papers

Creep Performance and Microstructure Evolution of IN617 at 950 °C for VHTR Applications

Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A002, August 8–12, 2022

Paper No: ICONE29-88939

DOI: https://doi.org/10.1115/ICONE29-88939

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Topics: Creep, Very high temperature reactors

Proceedings Papers

Research on the Influence of Girth Weld Joint Matching Degree on the Safety Performance of High Steel Grade Pipeline Based on ASME Local Strain Limit Criterion

Xin Liu, Liang Sun, Yongsheng Xu, Haitao Wang, Guide Deng

Proc. ASME. PVP2022, Volume 2: Computer Technology and Bolted Joints; Design and Analysis, V002T02A010, July 17–22, 2022

Paper No: PVP2022-84636

DOI: https://doi.org/10.1115/PVP2022-84636

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Topics: Mechanical properties, Pipelines, Safety, Steel, Pipes, Pressure, Base metals, Fracture (Materials), Computer simulation, Damage

Proceedings Papers

Study on the Transport Mechanism and Troubleshooting Analysis of Spherical Fuel in High Temperature Gas Cooled Reactor

Jinhua Wang, Yuchen Hao, Yue Li, Bin Wu, Haitao Wang, Tao Ma

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, V001T02A002, August 4–6, 2021

Paper No: ICONE28-63134

DOI: https://doi.org/10.1115/ICONE28-63134

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Topics: Fuels, Gas cooled reactors, High temperature, Nuclear power, Transportation systems

Proceedings Papers

Investigation and Design of Energy-Absorbing Structure in Nuclear Fuel Cask

Yuchen Hao, Yue Li, Jinhua Wang, Bin Wu, Tao Ma, Haitao Wang

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, V003T11A007, August 4–6, 2021

Paper No: ICONE28-63388

DOI: https://doi.org/10.1115/ICONE28-63388

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Topics: Design, Nuclear fuels, Transportation systems, Fuels, Metals, Safety, High temperature, Construction, Containers, Economics

Proceedings Papers

Study on the Structural Evaluation and Optimization of Spent Nuclear Fuel Cask

Yuchen Hao, Jinhua Wang, Yue Li, Bin Wu, Haitao Wang, Tao Ma

Paper No: ICONE28-63369

DOI: https://doi.org/10.1115/ICONE28-63369

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Topics: Nuclear power, Optimization, Spent nuclear fuels, Transportation systems

Journal Articles

Performance Analysis of Wave Rotor Based on Response Surface Optimization Method

Peiqi Liu, Mingyu Feng, Xinyu Liu, Haitao Wang, Dapeng Hu

J. Energy Resour. Technol. June 2022, 144(6): 061302.

Paper No: JERT-21-1188

DOI: https://doi.org/10.1115/1.4051758

Published Online: August 4, 2021

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Topics: Optimization, Pressure, Rotors, Waves, Entropy, Response surface methodology

Proceedings Papers

Study on the Impact Limiter Design in Spent Fuel Transfer Cask in Nuclear Power Plants

Yuchen Hao, Yue Li, Jinhua Wang, Bin Wu, Haitao Wang

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, V001T05A006, August 4–5, 2020

Paper No: ICONE2020-16157

DOI: https://doi.org/10.1115/ICONE2020-16157

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Topics: Cushioning materials, Design, Nuclear power stations, Spent nuclear fuels

Journal Articles

Fault Evolution Characteristic Analysis of Planetary Gear Based on Multidimensional Nonlinear Frequency Response

Haitao Wang, Zhimao Tao, Lichen Shi, Zhenya Kang

J. Comput. Nonlinear Dynam. April 2019, 14(4): 041007.

Paper No: CND-18-1296

DOI: https://doi.org/10.1115/1.4042634

Published Online: February 15, 2019

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Topics: Frequency response, Nonlinear systems, Planetary gears, Volterra series, Fracture (Materials), Mechanical drives, Signals, Algorithms

Proceedings Papers

Comparison of Two Ductile Crack Propagation Models of GTN and CZM for Pipe Steel Fracture

Junqiang Wang, Haitao Wang, Nan Lin, Honglian Ma, Jinlong Wang

Proc. ASME. PVP2018, Volume 6A: Materials and Fabrication, V06AT06A004, July 15–20, 2018

Paper No: PVP2018-84689

DOI: https://doi.org/10.1115/PVP2018-84689

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Topics: Ductile fracture, Fracture (Materials), Fracture (Process), Pipes, Steel, Crack propagation, Damage, Shapes, Accuracy and precision, Cohesion

Proceedings Papers

Filtration Technology Research of Graphite Dust Produced in Spent Fuel Transportation Process in HTR-PM

Jinhua Wang, Bing Wang, Bin Wu, Yue Li, Haitao Wang

Proc. ASME. ICONE26, Volume 2: Plant Systems, Structures, Components, and Materials; Risk Assessments and Management, V002T03A001, July 22–26, 2018

Paper No: ICONE26-81022

DOI: https://doi.org/10.1115/ICONE26-81022

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Topics: Dust, Filtration, Graphite, Spent nuclear fuels, Transportation systems, Fuels, Gas cooled reactors, High temperature, Nuclear power, Pipelines

Proceedings Papers

Design of the Process and Effluent Radiation Monitoring System of HTR-PM

Feng Xie, Wenqian Li, Zhihui Li, Jianzhu Cao, Hong Li, Jiejuan Tong, Haitao Wang

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, V001T03A031, June 26–30, 2016

Paper No: ICONE24-61008

DOI: https://doi.org/10.1115/ICONE24-61008

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Topics: Design, Radiation measurement, Pressurized water reactors, Very high temperature reactors, Carbon, Coolants, Dust, Fuels, Helium, Nuclear fission

Proceedings Papers

LBLOCA Analysis of CPR1000 NPP With Advanced Accumulator

Hongwei Hu, Jianqiang Shan, Junli Gou, Bo Zhang, Haitao Wang, Zijiang Yang

Proc. ASME. ICONE21, Volume 4: Thermal Hydraulics, V004T09A094, July 29–August 2, 2013

Paper No: ICONE21-16480

DOI: https://doi.org/10.1115/ICONE21-16480

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Topics: Nuclear power stations, Secondary cells, Flow (Dynamics), Temperature, Accidents, Safety, Cladding systems (Building), Design, Pressure, Pressure drop

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

The Reliability Prediction of HTR’s Graphite Component in Various Temperature and Neutron Dose Levels

Xiang Fang, Haitao Wang, Xingtuan Yang, Suyuan Yu

Proc. ASME. ICONE21, Volume 2: Plant Systems, Construction, Structures and Components; Next Generation Reactors and Advanced Reactors, V002T03A028, July 29–August 2, 2013

Paper No: ICONE21-15574

DOI: https://doi.org/10.1115/ICONE21-15574

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Topics: Graphite, Neutrons, Reliability, Temperature, Bricks, High temperature, Irradiation (Radiation exposure), Stress, Constitutive equations, Failure

Proceedings Papers

Experiment Study on Collision of Graphite Dowel-Brick Structures

Lie Jin, Libin Sun, Hongtao Wang, Haitao Wang, Xinxin Wu, Shaopeng Ma

Proc. ASME. ICONE21, Volume 2: Plant Systems, Construction, Structures and Components; Next Generation Reactors and Advanced Reactors, V002T03A045, July 29–August 2, 2013

Paper No: ICONE21-16283

DOI: https://doi.org/10.1115/ICONE21-16283

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Topics: Bricks, Collisions (Physics), Graphite

Proceedings Papers

A Three-Dimensional Rigid-Body Model for Seismic Analysis of the Pebble-Bed HTR Graphite Core Structure

Chuan Zeng, Haitao Wang

Proc. ASME. ICONE21, Volume 2: Plant Systems, Construction, Structures and Components; Next Generation Reactors and Advanced Reactors, V002T03A035, July 29–August 2, 2013

Paper No: ICONE21-15896

DOI: https://doi.org/10.1115/ICONE21-15896

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Topics: Graphite, Seismic analysis, Bricks, Shapes, Stress, Center of mass, Collisions (Physics), Computers, Degrees of freedom, Dynamic analysis

Proceedings Papers

Study on Temperature Distribution of Pebble-Bed HTR Fuel Element by Using Boundary Element Method

Haitao Wang, Xin Wang

Proc. ASME. PVP2013, Volume 6B: Materials and Fabrication, V06BT06A004, July 14–18, 2013

Paper No: PVP2013-97454

DOI: https://doi.org/10.1115/PVP2013-97454

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Topics: Boundary element methods, Fuels, Temperature distribution, Particulate matter, Temperature, Graphite, Computation, Computers, Design, Nuclear fuels

Proceedings Papers

Seismic Test and Analyses on Double-Layer Model of HTR-PM Graphite Structure

Libin Sun, Li Shi, Hongtao Wang, Haitao Wang, Yuqin Hu, Zhensheng Zhang

Proc. ASME. ICONE20-POWER2012, Volume 2: Plant Systems, Structures, and Components; Safety and Security; Next Generation Systems; Heat Exchangers and Cooling Systems, 165-173, July 30–August 3, 2012

Paper No: ICONE20-POWER2012-54961

DOI: https://doi.org/10.1115/ICONE20-POWER2012-54961

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Topics: Graphite

Proceedings Papers

An Experimental Study on Fracture Toughness of a Fine-Grained Isotropic Graphite

Hongtao Wang, Libin Sun, Haitao Wang, Li Shi, Zhensheng Zhang

Proc. ASME. ICONE20-POWER2012, Volume 2: Plant Systems, Structures, and Components; Safety and Security; Next Generation Systems; Heat Exchangers and Cooling Systems, 175-179, July 30–August 3, 2012

Paper No: ICONE20-POWER2012-55008

DOI: https://doi.org/10.1115/ICONE20-POWER2012-55008

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Topics: Fracture toughness, Graphite

Proceedings Papers

Effect of Irradiation Deformation and Graphite Varieties on the Irradiation Equivalent Stress and Life of Nuclear Graphite

Xiang Fang, Haitao Wang, Suyuan Yu

Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 5, 697-700, May 17–21, 2010

Paper No: ICONE18-30359

DOI: https://doi.org/10.1115/ICONE18-30359

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Topics: Deformation, Graphite, Irradiation (Radiation exposure), Stress, Creep, High temperature, Finite element analysis, Mechanical properties, Neutrons, Thermal properties

Journal citation

NARROW

Creep Performance and Microstructure Evolution of IN617 at 950 °C for VHTR Applications

Research on the Influence of Girth Weld Joint Matching Degree on the Safety Performance of High Steel Grade Pipeline Based on ASME Local Strain Limit Criterion

Study on the Transport Mechanism and Troubleshooting Analysis of Spherical Fuel in High Temperature Gas Cooled Reactor

Investigation and Design of Energy-Absorbing Structure in Nuclear Fuel Cask

Study on the Structural Evaluation and Optimization of Spent Nuclear Fuel Cask

Performance Analysis of Wave Rotor Based on Response Surface Optimization Method

Study on the Impact Limiter Design in Spent Fuel Transfer Cask in Nuclear Power Plants

Fault Evolution Characteristic Analysis of Planetary Gear Based on Multidimensional Nonlinear Frequency Response

Comparison of Two Ductile Crack Propagation Models of GTN and CZM for Pipe Steel Fracture

Filtration Technology Research of Graphite Dust Produced in Spent Fuel Transportation Process in HTR-PM

Design of the Process and Effluent Radiation Monitoring System of HTR-PM

LBLOCA Analysis of CPR1000 NPP With Advanced Accumulator

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

The Reliability Prediction of HTR’s Graphite Component in Various Temperature and Neutron Dose Levels

Experiment Study on Collision of Graphite Dowel-Brick Structures

A Three-Dimensional Rigid-Body Model for Seismic Analysis of the Pebble-Bed HTR Graphite Core Structure

Study on Temperature Distribution of Pebble-Bed HTR Fuel Element by Using Boundary Element Method

Seismic Test and Analyses on Double-Layer Model of HTR-PM Graphite Structure

An Experimental Study on Fracture Toughness of a Fine-Grained Isotropic Graphite

Effect of Irradiation Deformation and Graphite Varieties on the Irradiation Equivalent Stress and Life of Nuclear Graphite

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