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Proceedings Papers

Investigation of the Fuel Element Damage Monitoring Technology in HTGRs and PWRs

Rui Nie, Yu Wang, Feng Xie, Shan Qing, Jianzhu Cao

Proc. ASME. ICONE29, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A002, August 8–12, 2022

Paper No: ICONE29-88883

DOI: https://doi.org/10.1115/ICONE29-88883

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Topics: Damage, Fuels, Nuclides, Pressurized water reactors, Very high temperature reactors

Proceedings Papers

Effects of Stoichiometry and High-Temperature Annealing on Zirconium Carbide Coating Layer in TRISO Particles

Xinyu Cheng, Rongzheng Liu, Bing Liu, Xu Yang, Malin Liu, Jiaxing Chang, Youlin Shao

Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A066, August 8–12, 2022

Paper No: ICONE29-92858

DOI: https://doi.org/10.1115/ICONE29-92858

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Topics: Annealing, Coatings, Fuels, High temperature, Particulate matter, Stoichiometry, Very high temperature reactors, Zirconium

Proceedings Papers

Validation of NUIT for Decay Heat Predictions of PWR Spent Fuel Assemblies

Jian Li, Ruihan Li, Ding She, Jin'gang Liang, Lei Shi

Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A008, August 8–12, 2022

Paper No: ICONE29-89241

DOI: https://doi.org/10.1115/ICONE29-89241

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Topics: Heat, Pressurized water reactors, Spent nuclear fuels, Fuels, Neutrons, Boiling water reactors, Collapse, Cooling, Cross section (Physics), Density

Proceedings Papers

Preliminary Study on Corrosion Behavior and Mechanical Properties Of Inconel 617 in Impure Helium Environment of VHTR

Bin Du, Huaqiang Yin, Tao Ma, Haoxiang Li, Wei Zheng, Xuedong He

Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A003, August 8–12, 2022

Paper No: ICONE29-88943

DOI: https://doi.org/10.1115/ICONE29-88943

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Topics: Corrosion, Helium, Mechanical properties, Very high temperature reactors

Proceedings Papers

Preparation Method of ORIGEN2 Library for High Temperature Gas-Cooled Reactors

Irwan Liapto Simanullang, Katsuki Fukuhara, Keisuke Morita, Yuji Fukaya, Hai Quan Ho, Satoru Nagasumi, Kazuhiko Iigaki, Etsuo Ishitsuka, Nozomu Fujimoto

Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A023, August 8–12, 2022

Paper No: ICONE29-90802

DOI: https://doi.org/10.1115/ICONE29-90802

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Topics: Very high temperature reactors

Proceedings Papers

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

Yue Wang, Haitao Wang, Kejian Li

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

Control Strategies Evolution of Nuclear Plant: From Obninsk to HTR-PM

Zhonghua Cheng, Zhe Dong, Bowen Li

Proc. ASME. ICONE29, Volume 3: I&C, Digital Control, and Influence of Human Factors, V003T03A013, August 8–12, 2022

Paper No: ICONE29-91296

DOI: https://doi.org/10.1115/ICONE29-91296

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Topics: Nuclear power stations, Stress, Design, Economics , Safety, Carbon neutrality, Emissions, Very high temperature reactors

Proceedings Papers

Measurement of Unbalance Vibration Phase for Active Magnetic Bearing in High Temperature Gas-Cooled Reactor

Xiaoyu Bian, Zhengang Shi, Yangbo Zheng, Ni Mo, Lei Shi

Proc. ASME. ICONE29, Volume 3: I&C, Digital Control, and Influence of Human Factors, V003T03A025, August 8–12, 2022

Paper No: ICONE29-92646

DOI: https://doi.org/10.1115/ICONE29-92646

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Topics: Magnetic bearings, Very high temperature reactors, Vibration

Proceedings Papers

Machine Learning Modelling of Decay Heat Removal in High Temperature Gas-Cooled Reactor

Hao Wu, Liangzhi Yu, Fenglei Niu, Jiyuan Tu, Shengyao Jiang

Proc. ASME. ICONE29, Volume 7B: Thermal-Hydraulics and Safety Analysis, V07BT07A019, August 8–12, 2022

Paper No: ICONE29-92695

DOI: https://doi.org/10.1115/ICONE29-92695

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Topics: Heat, Machine learning, Modeling, Very high temperature reactors

Proceedings Papers

A Numerical Study on the Behaviors of Graphite Aerosol in the Containment During a Water Ingress Accident of High Temperature Gas-Cooled Reactors

Zhu Fang, Yiyang Zhang, Yating Wang, Zhikai You, Libin Sun, Xinxin Wu

Proc. ASME. ICONE29, Volume 8: Computational Fluid Dynamics (CFD) and Applications, V008T08A055, August 8–12, 2022

Paper No: ICONE29-92955

DOI: https://doi.org/10.1115/ICONE29-92955

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Topics: Accidents, Aerosols, Containment, Dust, Graphite, Very high temperature reactors, Water

Proceedings Papers

A CFD Method for Thermal-Hydraulic Calculation of Pebble Bed HTGRs

Junbing Zhu, Fubing Chen

Proc. ASME. ICONE29, Volume 8: Computational Fluid Dynamics (CFD) and Applications, V008T08A015, August 8–12, 2022

Paper No: ICONE29-91628

DOI: https://doi.org/10.1115/ICONE29-91628

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Topics: Computational fluid dynamics, Porous materials, Very high temperature reactors

Proceedings Papers

High Temperature Gas Cooled Reactor Steam Generator Research on Stress-Rupture Test of High Temperature Materials and Welded Joints

Shimei Bao

Proc. ASME. ICONE29, Volume 10: Advanced Methods of Manufacturing for Nuclear Reactors and Components, V010T10A039, August 8–12, 2022

Paper No: ICONE29-92956

DOI: https://doi.org/10.1115/ICONE29-92956

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Topics: Boilers, Gas cooled reactors, High temperature, High temperature materials, Rupture, Stress, Very high temperature reactors, Welded joints

Proceedings Papers

An Experimental Study on the Retention of Graphite Dust Aerosol in Pool Scrubbing and the Possible Application in HTGRs

Yating Wang, Yiyang Zhang, Zhu Fang, Xinxin Wu

Proc. ASME. ICONE29, Volume 11: Mitigation Strategies for Beyond Design Basis Events, V011T11A015, August 8–12, 2022

Paper No: ICONE29-92561

DOI: https://doi.org/10.1115/ICONE29-92561

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Topics: Aerosols, Decontamination, Dust, Graphite, Very high temperature reactors, Water

Proceedings Papers

Research on Wastewater Source Term in High-Temperature Gas-Cooled Reactor and the Environmental Impact at Inland Sites

Yichun Zhang, Chuan Li, Hong Li, Jianzhu Cao

Proc. ASME. ICONE29, Volume 5: Nuclear Safety, Security, and Cyber Security, V005T05A018, August 8–12, 2022

Paper No: ICONE29-91467

DOI: https://doi.org/10.1115/ICONE29-91467

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Topics: Corrosion, Sewage, Very high temperature reactors

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

Implementation and Comparison of Super Homogenization Method Based on Monte Carlo and Deterministic Codes

Yuan Yuan, Guoming Liu, Xiaodong Huo

Proc. ASME. ICONE29, Volume 14: Computer Code Verification and Validation; Nuclear Education and Public Acceptance, V014T14A006, August 8–12, 2022

Paper No: ICONE29-92520

DOI: https://doi.org/10.1115/ICONE29-92520

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Topics: Chemical kinetics, Cross section (Physics), Fast neutron reactors, Geometry, Manufacturing, Modeling, Physics, Relaxation (Physics), Very high temperature reactors

Proceedings Papers

Analysis and Improvement of Flow Field Calculation in Thermal Hydraulic Program for High Temperature Gas-Cooled Reactor

Dou Haoming, Lang Minggang, Zhang Han, She Ding

Proc. ASME. ICONE29, Volume 15: Student Paper Competition, V015T16A076, August 8–12, 2022

Paper No: ICONE29-92090

DOI: https://doi.org/10.1115/ICONE29-92090

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Topics: Errors, Flow (Dynamics), Very high temperature reactors

Proceedings Papers

Pulverization and Spheroidization of Natural Graphite Powder for The Matrix Graphite in High-Temperature Gas-Cooled Reactors

Xinlei Cao, Zhenming Lu, Yuxiao Feng, Juan Bai, Bing Liu, Ke Shen

Proc. ASME. ICONE29, Volume 15: Student Paper Competition, V015T16A096, August 8–12, 2022

Paper No: ICONE29-92524

DOI: https://doi.org/10.1115/ICONE29-92524

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Topics: Graphite, Very high temperature reactors

Proceedings Papers

Research on Operational Intervention Levels for the “Ground” Scenario in High Temperature Gas-Cooled Reactor

Ao Liu, Tao Liu, Liguo Zhang

Proc. ASME. ICONE29, Volume 15: Student Paper Competition, V015T16A084, August 8–12, 2022

Paper No: ICONE29-92197

DOI: https://doi.org/10.1115/ICONE29-92197

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Topics: Emergencies, Very high temperature reactors

Proceedings Papers

Dynamic Modeling of Nuclear Hydrogen Generation Plant Based on Multi-Modular High-Temperature Gas-Cooled Reactor

Junyi Li, Zhe Dong, Bowen Li, Xiaojin Huang

Proc. ASME. ICONE29, Volume 15: Student Paper Competition, V015T16A006, August 8–12, 2022

Paper No: ICONE29-88899

DOI: https://doi.org/10.1115/ICONE29-88899

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Topics: Combined heat and power, Dynamic modeling, Hydrogen, Very high temperature reactors

NARROW

Investigation of the Fuel Element Damage Monitoring Technology in HTGRs and PWRs

Effects of Stoichiometry and High-Temperature Annealing on Zirconium Carbide Coating Layer in TRISO Particles

Validation of NUIT for Decay Heat Predictions of PWR Spent Fuel Assemblies

Preliminary Study on Corrosion Behavior and Mechanical Properties Of Inconel 617 in Impure Helium Environment of VHTR

Preparation Method of ORIGEN2 Library for High Temperature Gas-Cooled Reactors

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

Control Strategies Evolution of Nuclear Plant: From Obninsk to HTR-PM

Measurement of Unbalance Vibration Phase for Active Magnetic Bearing in High Temperature Gas-Cooled Reactor

Machine Learning Modelling of Decay Heat Removal in High Temperature Gas-Cooled Reactor

A Numerical Study on the Behaviors of Graphite Aerosol in the Containment During a Water Ingress Accident of High Temperature Gas-Cooled Reactors

A CFD Method for Thermal-Hydraulic Calculation of Pebble Bed HTGRs

High Temperature Gas Cooled Reactor Steam Generator Research on Stress-Rupture Test of High Temperature Materials and Welded Joints

An Experimental Study on the Retention of Graphite Dust Aerosol in Pool Scrubbing and the Possible Application in HTGRs

Research on Wastewater Source Term in High-Temperature Gas-Cooled Reactor and the Environmental Impact at Inland Sites

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

Implementation and Comparison of Super Homogenization Method Based on Monte Carlo and Deterministic Codes

Analysis and Improvement of Flow Field Calculation in Thermal Hydraulic Program for High Temperature Gas-Cooled Reactor

Pulverization and Spheroidization of Natural Graphite Powder for The Matrix Graphite in High-Temperature Gas-Cooled Reactors

Research on Operational Intervention Levels for the “Ground” Scenario in High Temperature Gas-Cooled Reactor

Dynamic Modeling of Nuclear Hydrogen Generation Plant Based on Multi-Modular High-Temperature Gas-Cooled Reactor

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