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Proceedings Papers

Structural Analysis of a Reactor Vessel in a Sodium-Cooled Fast Reactor Under Extremely High Temperature Conditions

Hidemasa Yamano, Satoshi Futagami, Masanori Ando

Proc. ASME. ICONE29, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A034, August 8–12, 2022

Paper No: ICONE29-93231

DOI: https://doi.org/10.1115/ICONE29-93231

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Topics: Deformation, High temperature, Reactor vessels, Resilience, Sodium fast reactors, Structural analysis

Proceedings Papers

Coolability Evaluation of the Debris Bed on Core Catcher in a Sodium-Cooled Fast Reactor With a Whole Vessel Model

Hidemasa Yamano, Shigenobu Kubo, Kyohei Sasa, Akihiro Shibata, Edouard Hourcade, Jean François Dirat

Proc. ASME. ICONE29, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A035, August 8–12, 2022

Paper No: ICONE29-93244

DOI: https://doi.org/10.1115/ICONE29-93244

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Topics: Sodium fast reactors, Vessels, Circuits, Cooling systems, Fuels, Accidents, Cooling, Design, Dynamics (Mechanics), Flow (Dynamics)

Proceedings Papers

Study on Reactor Vessel Water Level Measurement Method for Emergency Decision-Making of Nuclear Power Plant

Yanming Shi, Zhenying Wang

Proc. ASME. ICONE29, Volume 12: Innovative and Smart Nuclear Power Plant Design, V012T12A027, August 8–12, 2022

Paper No: ICONE29-92804

DOI: https://doi.org/10.1115/ICONE29-92804

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Topics: Decision making, Emergencies, Nuclear power stations, Reactor vessels, Water

Proceedings Papers

Inadvertent Reactor Pit Flooding Risk Research on the Generation III Nuclear Power Plant

Lingmei Xiao, Bing Zhang, Ming Wang, Zhiwen Wang

Proc. ASME. ICONE29, Volume 13: Risk Assessments and Management, V013T13A036, August 8–12, 2022

Paper No: ICONE29-92450

DOI: https://doi.org/10.1115/ICONE29-92450

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Topics: Floods, Nuclear power stations, Reactor vessels, Risk, Vessels

Proceedings Papers

Nuclear Power Plant Design Optimization Based on Risk-Informed Method

Wenjing Li, Yu Liu, Gaopeng Wang, Xinli Yu

Proc. ASME. ICONE29, Volume 13: Risk Assessments and Management, V013T13A005, August 8–12, 2022

Paper No: ICONE29-89268

DOI: https://doi.org/10.1115/ICONE29-89268

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Topics: Nuclear design, Optimization, Risk, Design, Nuclear power stations, Accidents, Cavities, Vessels, China, Damage

Proceedings Papers

PSA Application in UK HPR1000 Numerical Targets Evaluation

Lingmei Xiao, Bing Zhang, Ming Wang, Jinkai Wang

Proc. ASME. ICONE29, Volume 13: Risk Assessments and Management, V013T13A038, August 8–12, 2022

Paper No: ICONE29-92462

DOI: https://doi.org/10.1115/ICONE29-92462

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Topics: Damage, Design, Dimensions, Floods, Nuclear power stations, Plant design, Radiation (Physics), Reactor vessels, Risk, Safety

Proceedings Papers

Flow Mixing Characteristics in Double Loop Reactor Pressure Vessel Under Accident Conditions

Guanhui Xie, Runcheng Li, Tianyi Wei, Zhikang Lin, Dongyang Li, Sichao Tan

Proc. ASME. ICONE29, Volume 15: Student Paper Competition, V015T16A010, August 8–12, 2022

Paper No: ICONE29-89228

DOI: https://doi.org/10.1115/ICONE29-89228

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Topics: Accidents, Boron, Flow (Dynamics), Fluids, Reactor vessels, Water, Pressure vessels, Coolants, Safety, Fluid dynamics

Proceedings Papers

Flow-Solid Coupling Analysis of Pressure Vessels on Floating Nuclear Power Plants

Yuchao Wang, Daogang Lu, Fei Zhao, Yu Liu

Proc. ASME. ICONE29, Volume 15: Student Paper Competition, V015T16A071, August 8–12, 2022

Paper No: ICONE29-92039

DOI: https://doi.org/10.1115/ICONE29-92039

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Topics: Displacement, Flow (Dynamics), Fluid structure interaction, Nuclear power stations, Pressure vessels, Sloshing, Stress, Vessels, Fast neutron reactors, Reactor vessels

Proceedings Papers

Sensitivity Calculation of Lower Shell Pressure Parameters in Advanced Nuclear Power Plant Accidents

Zhou Lanyu, Sun Yanyu, Zheng Yuntao, Yang Changjiang

Proc. ASME. ICONE29, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A004, August 8–12, 2022

Paper No: ICONE29-89165

DOI: https://doi.org/10.1115/ICONE29-89165

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Topics: Containment, Nuclear reactor accidents, Pressure, Shells, Temperature, Accidents, Boilers, Circuits, Coolants, Design

Proceedings Papers

Comparison Of Radiation Embrittlement Prediction Models for Reactor Pressure Vessel

Kexin Cai, Ping Huang, Wangjie Qian, Minyu Fan, Shuang Qi, Guodong Zhang, Yanwei Zhang

Proc. ASME. ICONE29, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A044, August 8–12, 2022

Paper No: ICONE29-92513

DOI: https://doi.org/10.1115/ICONE29-92513

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Topics: Embrittlement, Radiation (Physics), Reactor vessels

Proceedings Papers

Study on Ultrasonic Inspection Technology of Fastening Bolts of Reactor Internals

Jianbang Tang, Yukun Wu, Weiqiang Wang, Guanbing Ma, Chenming Zeng, Junlong Xu

Proc. ASME. ICONE29, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A048, August 8–12, 2022

Paper No: ICONE29-92644

DOI: https://doi.org/10.1115/ICONE29-92644

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Topics: Inspection, Nuclear power stations, Nondestructive evaluation, Design, High pressure (Physics), High temperature, In-service inspection, Irradiation (Radiation exposure), Nuclear fuels, Probes

Proceedings Papers

TCR Central Shutdown Rod Fine Motion Control

Venugopal K. Varma, Eliott Fountain, Earle Burkhardt, Sacit Cetiner, Dustin Ottinger

Proc. ASME. ICONE29, Volume 3: I&C, Digital Control, and Influence of Human Factors, V003T03A009, August 8–12, 2022

Paper No: ICONE29-90217

DOI: https://doi.org/10.1115/ICONE29-90217

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Topics: Electromagnets, Motion control, Design, Pressure vessels, Actuators, Artificial intelligence, Engineering prototypes, Engines, Gravity (Force), Helium

Proceedings Papers

Assessment of Passive Cooling Capability of the Westinghouse Lead Fast Reactor Under Station Blackout Conditions

Emre Tatli, Sung Jin Lee, Jun Liao, Paolo Ferroni

Proc. ASME. ICONE29, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A020, August 8–12, 2022

Paper No: ICONE29-91821

DOI: https://doi.org/10.1115/ICONE29-91821

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Topics: Cooling, Fast neutron reactors, Computational fluid dynamics, Design, Heat, Reactor vessels, Vessels, Water, Accidents, Accounting

Proceedings Papers

Development of Evaluation Method of Gas Entrainment on the Free Surface in the Reactor Vessel in Pool-Type Sodium-Cooled Fast Reactors -Gas Entrainment Judgment Based on Three-Dimensional Evaluation of Vortex Center Line and Distribution of Pressure Decrease

Kentarou Matsushita, Toshiki Ezure, Yasutomo Imai, Tatsuya Fujisaki, Masaaki Tanaka

Proc. ASME. ICONE29, Volume 8: Computational Fluid Dynamics (CFD) and Applications, V008T08A007, August 8–12, 2022

Paper No: ICONE29-90288

DOI: https://doi.org/10.1115/ICONE29-90288

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Topics: Evaluation methods, Pressure, Reactor vessels, Sodium fast reactors, Vortices

Proceedings Papers

Study on Forging Technology of Integrated Topcover Forging for AP1000 Reactor Pressure Vessel

Zhaoyin Li, Kai Dong, Zhiyong Tao

Proc. ASME. ICONE29, Volume 10: Advanced Methods of Manufacturing for Nuclear Reactors and Components, V010T10A043, August 8–12, 2022

Paper No: ICONE29-92966

DOI: https://doi.org/10.1115/ICONE29-92966

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Topics: Forging, Reactor vessels, Simulation

Proceedings Papers

Manufacturing Technology of Thick-Walled Integrated Cylinder With Large-Sized Side Nozzles for Nuclear Pressure Vessel

Shaofei Li

Proc. ASME. ICONE29, Volume 10: Advanced Methods of Manufacturing for Nuclear Reactors and Components, V010T10A028, August 8–12, 2022

Paper No: ICONE29-92302

DOI: https://doi.org/10.1115/ICONE29-92302

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Topics: Cylinders, Forging, Manufacturing technology, Nozzles, Reactor vessels

Proceedings Papers

Study on the Manufacturing Process of Large Super Alloy X-750 Forgings for Nuclear Equipment

Mei-fang Chen, Sheng-qiang Cao, Kai Dong

Proc. ASME. ICONE29, Volume 10: Advanced Methods of Manufacturing for Nuclear Reactors and Components, V010T10A019, August 8–12, 2022

Paper No: ICONE29-91791

DOI: https://doi.org/10.1115/ICONE29-91791

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Topics: Alloys, Forging, Forgings (Products), Manufacturing, Springs, Temperature, Grain size, Annealing, Creep, Fracture (Materials)

Proceedings Papers

Studies on the Principles for Developing In-Service Inspection Acceptance Standards of Reactor Pressure Vessels

Jun Pan, Chang Liu, Xihui Su

Proc. ASME. ICONE29, Volume 6: Nuclear Codes, Standards, Licensing, and Regulatory Issues, V006T06A013, August 8–12, 2022

Paper No: ICONE29-93037

DOI: https://doi.org/10.1115/ICONE29-93037

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Topics: Acceptance criteria, In-service inspection, Reactor vessels, Safety

Proceedings Papers

Codes Comparative Study on Mechanical Properties of Core Forgings of Reactor Pressure Vessel

Hao Yu, Yinbiao He, Xinxin Wu, Shenjie Gu, Xin Liu, Hongchang Wang

Proc. ASME. ICONE29, Volume 6: Nuclear Codes, Standards, Licensing, and Regulatory Issues, V006T06A003, August 8–12, 2022

Paper No: ICONE29-90363

DOI: https://doi.org/10.1115/ICONE29-90363

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Topics: Forgings (Products), Mechanical properties, Reactor vessels

Proceedings Papers

Fluid-Thermal-Mechanical Coupling Analysis of the Reactor Vessel of Natural Circulation Lead-Cooled Fast Reactor SNCLFR-100

Wenshun Duan, Kefan Zhang, Hongli Chen

Proc. ASME. ICONE29, Volume 7A: Thermal-Hydraulics and Safety Analysis, V07AT07A050, August 8–12, 2022

Paper No: ICONE29-91709

DOI: https://doi.org/10.1115/ICONE29-91709

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Topics: Fast neutron reactors, Fluids, Reactor vessels

NARROW

Structural Analysis of a Reactor Vessel in a Sodium-Cooled Fast Reactor Under Extremely High Temperature Conditions

Coolability Evaluation of the Debris Bed on Core Catcher in a Sodium-Cooled Fast Reactor With a Whole Vessel Model

Study on Reactor Vessel Water Level Measurement Method for Emergency Decision-Making of Nuclear Power Plant

Inadvertent Reactor Pit Flooding Risk Research on the Generation III Nuclear Power Plant

Nuclear Power Plant Design Optimization Based on Risk-Informed Method

PSA Application in UK HPR1000 Numerical Targets Evaluation

Flow Mixing Characteristics in Double Loop Reactor Pressure Vessel Under Accident Conditions

Flow-Solid Coupling Analysis of Pressure Vessels on Floating Nuclear Power Plants

Sensitivity Calculation of Lower Shell Pressure Parameters in Advanced Nuclear Power Plant Accidents

Comparison Of Radiation Embrittlement Prediction Models for Reactor Pressure Vessel

Study on Ultrasonic Inspection Technology of Fastening Bolts of Reactor Internals

TCR Central Shutdown Rod Fine Motion Control

Assessment of Passive Cooling Capability of the Westinghouse Lead Fast Reactor Under Station Blackout Conditions

Development of Evaluation Method of Gas Entrainment on the Free Surface in the Reactor Vessel in Pool-Type Sodium-Cooled Fast Reactors -Gas Entrainment Judgment Based on Three-Dimensional Evaluation of Vortex Center Line and Distribution of Pressure Decrease

Study on Forging Technology of Integrated Topcover Forging for AP1000 Reactor Pressure Vessel

Manufacturing Technology of Thick-Walled Integrated Cylinder With Large-Sized Side Nozzles for Nuclear Pressure Vessel

Study on the Manufacturing Process of Large Super Alloy X-750 Forgings for Nuclear Equipment

Studies on the Principles for Developing In-Service Inspection Acceptance Standards of Reactor Pressure Vessels

Codes Comparative Study on Mechanical Properties of Core Forgings of Reactor Pressure Vessel

Fluid-Thermal-Mechanical Coupling Analysis of the Reactor Vessel of Natural Circulation Lead-Cooled Fast Reactor SNCLFR-100

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