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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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-93231
https://doi.org/10.1115/ICONE29-93231
View Paper titled, Structural Analysis of a Reactor Vessel in a Sodium-Cooled Fast Reactor Under Extremely High Temperature Conditions
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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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-93244
https://doi.org/10.1115/ICONE29-93244
View Paper titled, Coolability Evaluation of the Debris Bed on Core Catcher in a Sodium-Cooled Fast Reactor With a Whole Vessel Model
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Topics: Sodium fast reactors, Vessels, Circuits, Cooling systems, Fuels, Accidents, Cooling, Design, Dynamics (Mechanics), Flow (Dynamics)
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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-90288
https://doi.org/10.1115/ICONE29-90288
View Paper titled, 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
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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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92966
https://doi.org/10.1115/ICONE29-92966
View Paper titled, Study on Forging Technology of Integrated Topcover Forging for AP1000 Reactor Pressure Vessel
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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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92302
https://doi.org/10.1115/ICONE29-92302
View Paper titled, Manufacturing Technology of Thick-Walled Integrated Cylinder With Large-Sized Side Nozzles for Nuclear Pressure Vessel
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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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-91791
https://doi.org/10.1115/ICONE29-91791
View Paper titled, Study on the Manufacturing Process of Large Super Alloy X-750 Forgings for Nuclear Equipment
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Topics: Alloys, Forging, Forgings (Products), Manufacturing, Springs, Temperature, Grain size, Annealing, Creep, Fracture (Materials)
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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92804
https://doi.org/10.1115/ICONE29-92804
View Paper titled, Study on Reactor Vessel Water Level Measurement Method for Emergency Decision-Making of Nuclear Power Plant
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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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92450
https://doi.org/10.1115/ICONE29-92450
View Paper titled, Inadvertent Reactor Pit Flooding Risk Research on the Generation III Nuclear Power Plant
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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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-89268
https://doi.org/10.1115/ICONE29-89268
View Paper titled, Nuclear Power Plant Design Optimization Based on Risk-Informed Method
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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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92462
https://doi.org/10.1115/ICONE29-92462
View Paper titled, PSA Application in UK HPR1000 Numerical Targets Evaluation
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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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-89228
https://doi.org/10.1115/ICONE29-89228
View Paper titled, Flow Mixing Characteristics in Double Loop Reactor Pressure Vessel Under Accident Conditions
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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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92039
https://doi.org/10.1115/ICONE29-92039
View Paper titled, Flow-Solid Coupling Analysis of Pressure Vessels on Floating Nuclear Power Plants
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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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-89165
https://doi.org/10.1115/ICONE29-89165
View Paper titled, Sensitivity Calculation of Lower Shell Pressure Parameters in Advanced Nuclear Power Plant Accidents
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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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92513
https://doi.org/10.1115/ICONE29-92513
View Paper titled, Comparison Of Radiation Embrittlement Prediction Models for Reactor Pressure Vessel
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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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92644
https://doi.org/10.1115/ICONE29-92644
View Paper titled, Study on Ultrasonic Inspection Technology of Fastening Bolts of Reactor Internals
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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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-90217
https://doi.org/10.1115/ICONE29-90217
View Paper titled, TCR Central Shutdown Rod Fine Motion Control
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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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-91821
https://doi.org/10.1115/ICONE29-91821
View Paper titled, Assessment of Passive Cooling Capability of the Westinghouse Lead Fast Reactor Under Station Blackout Conditions
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Topics: Cooling, Fast neutron reactors, Computational fluid dynamics, Design, Heat, Reactor vessels, Vessels, Water, Accidents, Accounting
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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-93037
https://doi.org/10.1115/ICONE29-93037
View Paper titled, Studies on the Principles for Developing In-Service Inspection Acceptance Standards of Reactor Pressure Vessels
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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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-90363
https://doi.org/10.1115/ICONE29-90363
View Paper titled, Codes Comparative Study on Mechanical Properties of Core Forgings of Reactor Pressure Vessel
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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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-91709
https://doi.org/10.1115/ICONE29-91709
View Paper titled, Fluid-Thermal-Mechanical Coupling Analysis of the Reactor Vessel of Natural Circulation Lead-Cooled Fast Reactor SNCLFR-100
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Topics: Fast neutron reactors, Fluids, Reactor vessels