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Proceedings Papers

Design and Validation on Preload of Manway Bolt for Pressurizer of Nuclear Power Plant Under Hydrotest Condition

Tao Chen, Guangming Xiong, Guanhua Fu, Xiaolong Zhao, Defu Wang, Yongqiang Zhang, Enming Liang
Proc. ASME. ICONE29, Volume 12: Innovative and Smart Nuclear Power Plant Design, V012T12A009, August 8–12, 2022
Paper No: ICONE29-91714
DOI: https://doi.org/10.1115/ICONE29-91714
View Paper titled, Design and Validation on Preload of Manway Bolt for Pressurizer of Nuclear Power Plant Under Hydrotest Condition
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Topics: Design, Finite element analysis, Nuclear power stations, Stress, Bolted flanges, Flanges, Coolants, Engineering prototypes, Gaskets, Leakage
Proceedings Papers

Comparative Study on Creep-Fatigue Damage Assessment Between R5 Procedures and a Full Inelastic Analysis

Antony M. Hurst, Louis C. W. Chang, Nak-Kyun Cho
Proc. ASME. ICONE29, Volume 12: Innovative and Smart Nuclear Power Plant Design, V012T12A008, August 8–12, 2022
Paper No: ICONE29-91707
DOI: https://doi.org/10.1115/ICONE29-91707
View Paper titled, Comparative Study on Creep-Fatigue Damage Assessment Between R5 Procedures and a Full Inelastic Analysis
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Topics: Creep, Damage assessment, Fatigue, Inelastic analysis, Stress, Damage, Elastic analysis, Cracking (Materials), Fracture (Process), Geometry
Proceedings Papers

Research on Structural Optimization Technology of Fuel Assembly Parts Based on Topology and Optimal Design

Huabin Fan, Shiyin Xu, Huili Jia
Proc. ASME. ICONE29, Volume 12: Innovative and Smart Nuclear Power Plant Design, V012T12A041, August 8–12, 2022
Paper No: ICONE29-93368
DOI: https://doi.org/10.1115/ICONE29-93368
View Paper titled, Research on Structural Optimization Technology of Fuel Assembly Parts Based on Topology and Optimal Design
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Topics: Design, Fuels, Manufacturing, Structural optimization, Topology, Nozzles, Pressure drop, Stress, Coolants, Flow (Dynamics)
Proceedings Papers

Research on Risk Assessment of Heavy Load Drops in Nuclear Power Plants

Chao Ma, Yiming Wang, Churan Feng, Jian Yang
Proc. ASME. ICONE29, Volume 13: Risk Assessments and Management, V013T13A002, August 8–12, 2022
Paper No: ICONE29-89056
DOI: https://doi.org/10.1115/ICONE29-89056
View Paper titled, Research on Risk Assessment of Heavy Load Drops in Nuclear Power Plants
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Topics: Nuclear power stations, Probabilistic safety assessment, Risk assessment, Stress
Proceedings Papers

Affecting Factors and Aspects of Developing Nuclear Public Acceptance Strategies

Haomiao Lin
Proc. ASME. ICONE29, Volume 14: Computer Code Verification and Validation; Nuclear Education and Public Acceptance, V014T15A004, August 8–12, 2022
Paper No: ICONE29-90522
DOI: https://doi.org/10.1115/ICONE29-90522
View Paper titled, Affecting Factors and Aspects of Developing Nuclear Public Acceptance Strategies
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Topics: Carbon, Climate change, Construction, Nuclear power, Safety, Stress, Sustainable development
Proceedings Papers

Dynamic Modeling and Reactor Power Control of a Natural Circulation Pool-Type Lead-Cooled Fast Reactor

Yun Feng, Pei-Wei Sun, Xinyu Wei
Proc. ASME. ICONE29, Volume 15: Student Paper Competition, V015T16A104, August 8–12, 2022
Paper No: ICONE29-92872
DOI: https://doi.org/10.1115/ICONE29-92872
View Paper titled, Dynamic Modeling and Reactor Power Control of a Natural Circulation Pool-Type Lead-Cooled Fast Reactor
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Topics: Dynamic modeling, Fast neutron reactors, Control systems, Stress, Circuits, Design, Thermal energy, Coolants, Cooling, Flow (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
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

Study on Stress Prediction Method of Explosion-Proof Electric Heater in Nuclear Power Plant

Yiwei Chen, Jiashun Ruan, Yan Wang, Qiuhong Zhou, Haitao Li
Proc. ASME. ICONE29, Volume 7A: Thermal-Hydraulics and Safety Analysis, V07AT07A041, August 8–12, 2022
Paper No: ICONE29-91519
DOI: https://doi.org/10.1115/ICONE29-91519
View Paper titled, Study on Stress Prediction Method of Explosion-Proof Electric Heater in Nuclear Power Plant
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Topics: Explosions, Nuclear power stations, Stress
Proceedings Papers

Simulation of Detection Efficiency of High Integrity Container Gamma Scanning Device for Nuclear Power Plant Based on CZT Detector

Wenzhang Xie, Jia Huang, Chenyu Shan, Qingxin Lei, Kang Chang, Hao Zhou, Feng Liu, Peng Lin, Xiajie Liu, Li Li
Proc. ASME. ICONE29, Volume 9: Decontamination and Decommissioning, Radiation Protection, and Waste Management, V009T09A012, August 8–12, 2022
Paper No: ICONE29-91233
DOI: https://doi.org/10.1115/ICONE29-91233
View Paper titled, Simulation of Detection Efficiency of High Integrity Container Gamma Scanning Device for Nuclear Power Plant Based on CZT Detector
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Topics: Containers, Nuclear power stations, Sensors, Simulation, Density, Radioactive wastes, Chemical stability, Engineering standards, Evaporation, Filtration
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
View Paper titled, High Temperature Gas Cooled Reactor Steam Generator Research on Stress-Rupture Test of High Temperature Materials and Welded Joints
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Topics: Boilers, Gas cooled reactors, High temperature, High temperature materials, Rupture, Stress, Very high temperature reactors, Welded joints
Proceedings Papers

Study on Multi-Objective Optimization Design of LP Section for 1000MW Class Nuclear Turbines

Yifeng Hu, Zhiqiang Hu
Proc. ASME. ICONE29, Volume 10: Advanced Methods of Manufacturing for Nuclear Reactors and Components, V010T10A013, August 8–12, 2022
Paper No: ICONE29-91474
DOI: https://doi.org/10.1115/ICONE29-91474
View Paper titled, Study on Multi-Objective Optimization Design of LP Section for 1000MW Class Nuclear Turbines
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Topics: Design, Pareto optimization, Turbines, Stress, Deformation, Optimization, Steam turbines, Design methodology, Weight (Mass), Buckling
Proceedings Papers

Study on the Application of Electromagnetic Stepping CRDM at Tilted Environment

Zhaohui Lu, Zewen Li, Jianming Zhou, Qingsong Liu
Proc. ASME. ICONE29, Volume 10: Advanced Methods of Manufacturing for Nuclear Reactors and Components, V010T10A005, August 8–12, 2022
Paper No: ICONE29-90150
DOI: https://doi.org/10.1115/ICONE29-90150
View Paper titled, Study on the Application of Electromagnetic Stepping CRDM at Tilted Environment
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Topics: Design, Engineering prototypes, Failure, Kinematics, Polishing equipment, Pressurized water reactors, Stress, Structural design, Surface finishing, Wear
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
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

Optimization in Heat Transfer Scheme for Load Rejection and Emergency Shutdown Conditions of Sodium Fast Reactor

Yang Yu, Jun Yang, Jin Wang, Xiaokun Wang, Wenjun Hu, Donghui Zhang
Proc. ASME. ICONE29, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A022, August 8–12, 2022
Paper No: ICONE29-91857
DOI: https://doi.org/10.1115/ICONE29-91857
View Paper titled, Optimization in Heat Transfer Scheme for Load Rejection and Emergency Shutdown Conditions of Sodium Fast Reactor
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Topics: Heat transfer, Optimization, Scram, Sodium fast reactors, Stress
Proceedings Papers

Seismic Analysis of the Scale Reactor Structure Model of a Lead-Bismuth-Cooled ADS Reactor

Gang Rong, He Zhu, Yi Yang
Proc. ASME. ICONE29, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A017, August 8–12, 2022
Paper No: ICONE29-91753
DOI: https://doi.org/10.1115/ICONE29-91753
View Paper titled, Seismic Analysis of the Scale Reactor Structure Model of a Lead-Bismuth-Cooled ADS Reactor
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Topics: Seismic analysis, Annulus, Design, Fluid structure interaction, Leakage, Cavities, Finite element analysis, Fluids, Metals, Shells
Proceedings Papers

Dynamic Analysis and Experimental Study of the Multi-Point Support Structure Based on Similar Theory Under Thermal Environment

Xi Deng, Qingsong Liu, Jianming Zhou, Chen Xi, Shuo Hou, Qiang Liu, Guangyao Lu, Xudong Wei, Liang Ni
Proc. ASME. ICONE29, Volume 5: Nuclear Safety, Security, and Cyber Security, V005T05A059, August 8–12, 2022
Paper No: ICONE29-93497
DOI: https://doi.org/10.1115/ICONE29-93497
View Paper titled, Dynamic Analysis and Experimental Study of the Multi-Point Support Structure Based on Similar Theory Under Thermal Environment
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Topics: Bearings, Clearances (Engineering), Computer simulation, Design, Dynamic analysis, Dynamics (Mechanics), High temperature, Manufacturing, Reliability, Risk
Proceedings Papers

On Multiaxial Strain Characteristics of Piping Systems Subjected to Earthquake Loads

Masaki Morishita, Akihito Otani
Proc. ASME. ICONE29, Volume 6: Nuclear Codes, Standards, Licensing, and Regulatory Issues, V006T06A002, August 8–12, 2022
Paper No: ICONE29-90172
DOI: https://doi.org/10.1115/ICONE29-90172
View Paper titled, On Multiaxial Strain Characteristics of Piping Systems Subjected to Earthquake Loads
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Topics: Cycles, Earthquake resistant design, Earthquakes, Fatigue, Pipes, Piping systems, Stress, Excitation, ASME Boiler and Pressure Vessel Code, Deformation
Proceedings Papers

Simulation Research on Safe Load-Reducing Operation Margin of Nuclear Power Unit With Clogging of the CFI Drum Net

Jinchao Liu, Yaozu Lin, Bijun Chen, Xue Lyu, Jiayi Li, Heng Zhang
Proc. ASME. ICONE29, Volume 5: Nuclear Safety, Security, and Cyber Security, V005T05A044, August 8–12, 2022
Paper No: ICONE29-92540
DOI: https://doi.org/10.1115/ICONE29-92540
View Paper titled, Simulation Research on Safe Load-Reducing Operation Margin of Nuclear Power Unit With Clogging of the CFI Drum Net
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Topics: Nuclear power, Pumps, Simulation, Stress
Proceedings Papers

Analysis and Evaluation of Performance for Enriched B 4 C Absorber Used as Control Rod

Kaiyuan Wang, Xiaohan Liu, Xin Jin
Proc. ASME. ICONE29, Volume 7A: Thermal-Hydraulics and Safety Analysis, V07AT07A021, August 8–12, 2022
Paper No: ICONE29-89917
DOI: https://doi.org/10.1115/ICONE29-89917
View Paper titled, Analysis and Evaluation of Performance for Enriched B 4 C Absorber Used as Control Rod
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Topics: Absorption, Boron, Cladding systems (Building), Corrosion resistance, Design, Fuels, Irradiation (Radiation exposure), Manufacturing, Neutrons, Nuclear fission
Proceedings Papers

Consideration of Human Factors in SGTR Mitigation Strategy

Miaomiao Xu, Runcheng Li, Yunyin Chen, Wenying Ji, Zhikang Lin
Proc. ASME. ICONE29, Volume 7A: Thermal-Hydraulics and Safety Analysis, V07AT07A023, August 8–12, 2022
Paper No: ICONE29-90151
DOI: https://doi.org/10.1115/ICONE29-90151
View Paper titled, Consideration of Human Factors in SGTR Mitigation Strategy
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Topics: Human factors, Pressurized water reactors, Safety, Design, Accidents, Boilers, Circuits, Containment, Rupture, Stress