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Proceedings Papers

Retracted: “Power Control System Design for Heat Pipe Cooled Reactor Based on Model Predictive Control” [2022 29th International Conference on Nuclear Engineering, Volume 15] Shenzhen, China and Virtual, Online, August 8–12, 2022, Conference Sponsors: Pressure Vessels and Piping Division, ISBN: 978-0-7918-8650-2, Copyright © 2022 by ASME. Paper No. ICONE29-89495, V015T16A014; 8 pages; doi: https://doi.org/10.1115/ICONE29-89495

ASME

Proc. ASME. ICONE29, Volume 15: Student Paper Competition, V015T16A014, August 8–12, 2022

Paper No: ICONE29-89495

DOI: https://doi.org/10.1115/ICONE29-89495

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Topics: China, Control systems, Design, Heat pipes, Nuclear engineering, Pipes, Predictive control, Pressure vessels

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

Design and Comparison of Drainage Technology Scheme for Multi-Purpose Modular Small Reactor Science and Technology Demonstration Project

Mao Yujia, Sheng Liyuan, Yang Ruobing, Bai Wei, Li Jing

Proc. ASME. ICONE29, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A014, August 8–12, 2022

Paper No: ICONE29-91546

DOI: https://doi.org/10.1115/ICONE29-91546

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Topics: Design, Drainage, Water

Proceedings Papers

3d Multi-Physics Numerical Coupling of Monte Carlo Neutronics and Thermal-Hydraulic for Solid Core

Qing Yang, Jianhua Xia, Xiaojing Liu, Qingquan Pan, Hui He, Tengfei Zhang

Proc. ASME. ICONE29, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A038, August 8–12, 2022

Paper No: ICONE29-94534

DOI: https://doi.org/10.1115/ICONE29-94534

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Topics: Physics, Neutrons, Simulation, Computational fluid dynamics, Computer simulation, Conceptual design, Coolants, Design, Nuclear design, Optimization

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

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Topics: Seismic analysis, Annulus, Design, Fluid structure interaction, Leakage, Cavities, Finite element analysis, Fluids, Metals, Shells

Proceedings Papers

Pre-Conceptual Core Design of a Micro-LBE-Cooled Fast Reactor

Eing Yee Yeoh, Menglu Liu, Zhen Luo, Xiaosong Chen, Linsen Li, Gang Zheng

Proc. ASME. ICONE29, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A008, August 8–12, 2022

Paper No: ICONE29-90903

DOI: https://doi.org/10.1115/ICONE29-90903

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Topics: Design, Fast neutron reactors

Proceedings Papers

Study on the Response of Prestressed Reinforced Concrete Slabs With High Reinforcement Ratio Under Low Speed Impact

Mengyan Song, Di Jiang, Changkai Li, Chaoqi Zhang, Xudong Zhi

Proc. ASME. ICONE29, Volume 5: Nuclear Safety, Security, and Cyber Security, V005T05A050, August 8–12, 2022

Paper No: ICONE29-92808

DOI: https://doi.org/10.1115/ICONE29-92808

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Topics: Concrete slabs, Reinforced concrete, Slabs, Displacement, Prestressed concrete, Containment, Nuclear power stations, Bonding, Computer software, Concretes

Proceedings Papers

The Applicability Analysis of Fusion Reactors and China Nuclear Safety Code HAF102

Yijie Qian, Chong Li

Proc. ASME. ICONE29, Volume 5: Nuclear Safety, Security, and Cyber Security, V005T05A026, August 8–12, 2022

Paper No: ICONE29-91692

DOI: https://doi.org/10.1115/ICONE29-91692

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Topics: China, Fusion reactors, Safety, Design, Defense industry, Nuclear design, Nuclear fission, Nuclear fusion, Nuclear reactors, Regulations

Proceedings Papers

Application of First-Order Method to Estimate Structural Integrity in a Probabilistic Form of Component Subjected to Thermal Transient for Optimization of Design Parameter

Satoshi Okajima, Takero Mori, Norihiro Kikuchi, Masaaki Tanaka, Masashi Miyazaki

Proc. ASME. ICONE29, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A001, August 8–12, 2022

Paper No: ICONE29-88933

DOI: https://doi.org/10.1115/ICONE29-88933

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Topics: Design, Failure, Optimization, Probability, Transients (Dynamics)

Proceedings Papers

Study on the Plutonium Holdup Measurement in Glove-Box

Yimei Cheng, Xiaoming Xu, Honghe Yin, Xinjun Li, Sijia Wang

Proc. ASME. ICONE29, Volume 5: Nuclear Safety, Security, and Cyber Security, V005T05A010, August 8–12, 2022

Paper No: ICONE29-90455

DOI: https://doi.org/10.1115/ICONE29-90455

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Topics: Design, Electronics, Measurement systems, Neutrons, Optimization, Sensors, Simulation, Stability

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

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Topics: Bearings, Clearances (Engineering), Computer simulation, Design, Dynamic analysis, Dynamics (Mechanics), High temperature, Manufacturing, Reliability, Risk

Proceedings Papers

Study of Application of Automatic Cooldown/Heatup Technology on CPR1000 Nuclear Power Plant

Wang Kai, Ming Jia Zhou, Wei Zhang

Proc. ASME. ICONE29, Volume 7A: Thermal-Hydraulics and Safety Analysis, V07AT07A037, August 8–12, 2022

Paper No: ICONE29-91242

DOI: https://doi.org/10.1115/ICONE29-91242

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Topics: Automatic control, Control systems, Cooling, Design, Heating, Heating and cooling, Nuclear power stations, Pressure, Simulation, Temperature

Proceedings Papers

Application of ALARP Concept in Nuclear Power Plant Design — A Case Study in HPR1000

Dongyuan Li, Shi Qing, Haiying Luo, Jinkai Wang, Jiaoshen Xu

Proc. ASME. ICONE29, Volume 6: Nuclear Codes, Standards, Licensing, and Regulatory Issues, V006T06A009, August 8–12, 2022

Paper No: ICONE29-92241

DOI: https://doi.org/10.1115/ICONE29-92241

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Topics: Design, Nuclear design, Risk, Licensing, Safety, Economics , Nuclear power stations, Plant design, Regulations, Self-evaluation

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

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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

Information Security Design of Nuclear Power Embedded Real-Time Operating System

Meng Li, Guilian Shi, Zhonggang Ma, Xiaowei Wang, Lichen Fan, Weiwei Dou

Proc. ASME. ICONE29, Volume 5: Nuclear Safety, Security, and Cyber Security, V005T05A003, August 8–12, 2022

Paper No: ICONE29-89240

DOI: https://doi.org/10.1115/ICONE29-89240

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Topics: Control systems, Design, Instrumentation, Nuclear power, Nuclear power stations, Security

Proceedings Papers

Research and Application of Diversity Design of Nuclear Power Plant Based on High-Frequency Occurring Accidents Mitigation

Jiaoshen Xu, Zhengjie Liu

Proc. ASME. ICONE29, Volume 5: Nuclear Safety, Security, and Cyber Security, V005T05A065, August 8–12, 2022

Paper No: ICONE29-93635

DOI: https://doi.org/10.1115/ICONE29-93635

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Topics: Accidents, Design, Failure, Nuclear power stations

Proceedings Papers

Analysis and Research of Code Revision for Design of Nuclear Safety Related Concrete Structures of Pressurized Water Reactor Nuclear Power Plants in China

Jun Huang, Weiguo Zhang, Xueyuan Liang, Feifei Wu, Jing Xu, Shaolin Zhang, Wen Yang, Zhiyao Tang

Proc. ASME. ICONE29, Volume 6: Nuclear Codes, Standards, Licensing, and Regulatory Issues, V006T06A018, August 8–12, 2022

Paper No: ICONE29-93834

DOI: https://doi.org/10.1115/ICONE29-93834

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Topics: China, Concretes, Design, Nuclear power stations, Pressurized water reactors, Safety

Proceedings Papers

Experimental Studies and Mechanical Properties Analysis of Three-Dimensional Oblique Rotating Friction Seismic Isolators

Saifeng Wu, Wenguang Liu, Wenfu He

Proc. ASME. ICONE29, Volume 5: Nuclear Safety, Security, and Cyber Security, V005T05A045, August 8–12, 2022

Paper No: ICONE29-92541

DOI: https://doi.org/10.1115/ICONE29-92541

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Topics: Friction, Mechanical properties, Bearings, Damage, Deformation, Design, Earthquakes, Errors, Rubber, Stiffness

Proceedings Papers

Research on Risk Characterization Method of Marine Biological Disaster Affecting Water Intake Safety of Nuclear Power Plant and Application of Design Protection

Yu Fan, Bai Jie, Xu Botao, Lv Xingbing, Li Yong, Zhang Xueqing

Proc. ASME. ICONE29, Volume 5: Nuclear Safety, Security, and Cyber Security, V005T05A047, August 8–12, 2022

Paper No: ICONE29-92742

DOI: https://doi.org/10.1115/ICONE29-92742

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Topics: Design, Disasters, Nuclear power, Nuclear power stations, Risk, Safety, Valuation, Water

Proceedings Papers

Margin Analysis of Conventional Island Under Beyond Design Basis External Flooding Scenario for NPP

Xingbing Lv, Shuangyang Liu, Hongyang Zhang, Run Lin

Proc. ASME. ICONE29, Volume 5: Nuclear Safety, Security, and Cyber Security, V005T05A035, August 8–12, 2022

Paper No: ICONE29-92151

DOI: https://doi.org/10.1115/ICONE29-92151

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Topics: Design, Floods, Nuclear power stations

NARROW

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

Design and Comparison of Drainage Technology Scheme for Multi-Purpose Modular Small Reactor Science and Technology Demonstration Project

3d Multi-Physics Numerical Coupling of Monte Carlo Neutronics and Thermal-Hydraulic for Solid Core

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

Pre-Conceptual Core Design of a Micro-LBE-Cooled Fast Reactor

Study on the Response of Prestressed Reinforced Concrete Slabs With High Reinforcement Ratio Under Low Speed Impact

The Applicability Analysis of Fusion Reactors and China Nuclear Safety Code HAF102

Application of First-Order Method to Estimate Structural Integrity in a Probabilistic Form of Component Subjected to Thermal Transient for Optimization of Design Parameter

Study on the Plutonium Holdup Measurement in Glove-Box

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

Study of Application of Automatic Cooldown/Heatup Technology on CPR1000 Nuclear Power Plant

Application of ALARP Concept in Nuclear Power Plant Design — A Case Study in HPR1000

On Multiaxial Strain Characteristics of Piping Systems Subjected to Earthquake Loads

Information Security Design of Nuclear Power Embedded Real-Time Operating System

Research and Application of Diversity Design of Nuclear Power Plant Based on High-Frequency Occurring Accidents Mitigation

Analysis and Research of Code Revision for Design of Nuclear Safety Related Concrete Structures of Pressurized Water Reactor Nuclear Power Plants in China

Experimental Studies and Mechanical Properties Analysis of Three-Dimensional Oblique Rotating Friction Seismic Isolators

Research on Risk Characterization Method of Marine Biological Disaster Affecting Water Intake Safety of Nuclear Power Plant and Application of Design Protection

Margin Analysis of Conventional Island Under Beyond Design Basis External Flooding Scenario for NPP

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