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Proceedings Papers

Research on Precision Water Reactor Fuel Servo Operation System

Li Ping, Peiqiang Deng, Wei Qian, Kaiyu Yang, Jiansong Zhai, Shuiyang Huang
Proc. ASME. ICONE29, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A041, August 8–12, 2022
Paper No: ICONE29-92493
https://doi.org/10.1115/ICONE29-92493
View Paper titled, Research on Precision Water Reactor Fuel Servo Operation System
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Topics: Nuclear fuels, Nuclear power stations, Servomechanisms, Water, Engines, Motors, Permanent magnets, Algorithms, Control algorithms, Control theory
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
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

Analysis of Hydrogenation Properties of Nuclear Fuel Zirconium Alloy Cladding

Lin Qin
Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A009, August 8–12, 2022
Paper No: ICONE29-89580
https://doi.org/10.1115/ICONE29-89580
View Paper titled, Analysis of Hydrogenation Properties of Nuclear Fuel Zirconium Alloy Cladding
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Topics: Accidents, Cladding systems (Building), Nuclear fuels, Zirconium alloys
Proceedings Papers

Patent Perspective on the Development of Metal Nuclear Fuel Technology

Haoliang Zhong, Yu Si, Xiaofei Chen, Yading Zhang, Ran Su
Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A076, August 8–12, 2022
Paper No: ICONE29-93138
https://doi.org/10.1115/ICONE29-93138
View Paper titled, Patent Perspective on the Development of Metal Nuclear Fuel Technology
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Topics: Metals, Nuclear fuels, Patents
Proceedings Papers

Structural Design and Dynamic Analysis of the Heat Exchanger Used in Nuclear Fuel Test Loop

Huang Gang, Sun Sheng, Pan Liangming, Si Junping
Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A059, August 8–12, 2022
Paper No: ICONE29-92625
https://doi.org/10.1115/ICONE29-92625
View Paper titled, Structural Design and Dynamic Analysis of the Heat Exchanger Used in Nuclear Fuel Test Loop
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Topics: Design, Dynamic analysis, Heat exchangers, Nuclear fuels, Stress, Structural design
Proceedings Papers

Application and Prospect of Additive Manufacturing Technology in Nuclear Fuel Assembly Fabrication

Jie Ding, Yixiong Zheng, Chen Ye, Cong Li
Proc. ASME. ICONE29, Volume 10: Advanced Methods of Manufacturing for Nuclear Reactors and Components, V010T10A016, August 8–12, 2022
Paper No: ICONE29-91618
https://doi.org/10.1115/ICONE29-91618
View Paper titled, Application and Prospect of Additive Manufacturing Technology in Nuclear Fuel Assembly Fabrication
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Topics: Additive manufacturing, Design, Manufacturing, Nuclear fuels, Nuclear power stations, Pressurized water reactors
Proceedings Papers

Summary of Effects of Oxide Layer on Permeability Coefficient of Tritium

Ziling Zhou, Yu Wang, Jingni Guo, Feng Xie, Wenqian Li, Yanwei Wen, Bin Shan
Proc. ASME. ICONE29, Volume 15: Student Paper Competition, V015T16A039, August 8–12, 2022
Paper No: ICONE29-91275
https://doi.org/10.1115/ICONE29-91275
View Paper titled, Summary of Effects of Oxide Layer on Permeability Coefficient of Tritium
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Topics: Hydraulic conductivity, Very high temperature reactors, Fusion reactors, Hydrogen, Isotopes, Nuclear reactors, Coolants, Design, Diffusion (Physics), Engineering systems and industry applications
Proceedings Papers

Frequency Analysis of Liquid Metal Reactor Fuel Assemblies

Hui Fu, Daogang Lu, Yu Liu
Proc. ASME. ICONE29, Volume 7B: Thermal-Hydraulics and Safety Analysis, V07BT07A039, August 8–12, 2022
Paper No: ICONE29-93236
https://doi.org/10.1115/ICONE29-93236
View Paper titled, Frequency Analysis of Liquid Metal Reactor Fuel Assemblies
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Topics: Fuels, Liquid metals, Manufacturing, Nuclear fuels
Proceedings Papers

Application of Boron Feedback From BOA CIPS/CILC Analysis on Neutronic Models

Jesse Fisher, Gary Mangham, Christopher Briggs, Guoqiang Wang, Baocheng Zhang
Proc. ASME. ICONE29, Volume 7B: Thermal-Hydraulics and Safety Analysis, V07BT07A061, August 8–12, 2022
Paper No: ICONE29-94476
https://doi.org/10.1115/ICONE29-94476
View Paper titled, Application of Boron Feedback From BOA CIPS/CILC Analysis on Neutronic Models
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Topics: Boron, Feedback, Physics, Fuels, Linkages, Pressurized water reactors, Boiling, Boron compounds, Corrosion, Cycles
Proceedings Papers

Optimal Design of Thermal Scheme for Liquid Metal Cooled High Flux Reactor Fuel Assembly

Rui Pan, Kefan Zhang, Xilin Zhang, Jian Deng, Yong Zhang, Dahuan Zhu, Hongli Chen
Proc. ASME. ICONE29, Volume 7B: Thermal-Hydraulics and Safety Analysis, V07BT07A013, August 8–12, 2022
Paper No: ICONE29-92497
https://doi.org/10.1115/ICONE29-92497
View Paper titled, Optimal Design of Thermal Scheme for Liquid Metal Cooled High Flux Reactor Fuel Assembly
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Topics: Design, Fuels, Liquid metals, Manufacturing, Nuclear fuels
Proceedings Papers

Research on Application of Additive Manufacturing Technology In Nuclear Fuel Assembly Field

Hua Li, Ti Yue, Fawen Zhu, Yuan Peng, Yun Li, Chunlan Huang, Youjia Zhang
Proc. ASME. ICONE28, Volume 2: Nuclear Fuels, Research, and Fuel Cycle; Nuclear Codes and Standards; Thermal-Hydraulics, V002T05A017, August 4–6, 2021
Paper No: ICONE28-65776
https://doi.org/10.1115/ICONE28-65776
View Paper titled, Research on Application of Additive Manufacturing Technology In Nuclear Fuel Assembly Field
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Topics: Additive manufacturing, Design, Fuels, Manufacturing, Nuclear fuels
Proceedings Papers

Risk Analysis of Gasification Process of Nuclear Fuel Manufacturing Facilities Based on FTA

Xiaowei Yang, Dan Lyu, Ji Que, Yuntao Liu, Shangui Zhao
Proc. ASME. ICONE28, Volume 2: Nuclear Fuels, Research, and Fuel Cycle; Nuclear Codes and Standards; Thermal-Hydraulics, V002T05A006, August 4–6, 2021
Paper No: ICONE28-63648
https://doi.org/10.1115/ICONE28-63648
View Paper titled, Risk Analysis of Gasification Process of Nuclear Fuel Manufacturing Facilities Based on FTA
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Topics: Fuel gasification, Nuclear fuels, Production facilities, Risk analysis
Proceedings Papers

Investigation and Design of Energy-Absorbing Structure in Nuclear Fuel Cask

Yuchen Hao, Yue Li, Jinhua Wang, Bin Wu, Tao Ma, Haitao Wang
Proc. ASME. ICONE28, Volume 3: Computational Fluid Dynamics (CFD); Verification and Validation; Advanced Methods of Manufacturing (AMM) for Nuclear Reactors and Components; Decontamination, Decommissioning, and Radioactive Waste Management; Beyond Design Basis and Nuclear Safety; Risk Informed Management and Regulation, V003T11A007, August 4–6, 2021
Paper No: ICONE28-63388
https://doi.org/10.1115/ICONE28-63388
View Paper titled, Investigation and Design of Energy-Absorbing Structure in Nuclear Fuel Cask
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Topics: Design, Nuclear fuels, Transportation systems, Fuels, Metals, Safety, High temperature, Construction, Containers, Economics
Proceedings Papers

Dropping-Rod Analysis of Control Rod in ADS Lead-Bismuth Alloy Zero-Power Reactor

Hui Fu, Daogang Lu, Yu Liu
Proc. ASME. ICONE28, Volume 3: Computational Fluid Dynamics (CFD); Verification and Validation; Advanced Methods of Manufacturing (AMM) for Nuclear Reactors and Components; Decontamination, Decommissioning, and Radioactive Waste Management; Beyond Design Basis and Nuclear Safety; Risk Informed Management and Regulation, V003T12A012, August 4–6, 2021
Paper No: ICONE28-64082
https://doi.org/10.1115/ICONE28-64082
View Paper titled, Dropping-Rod Analysis of Control Rod in ADS Lead-Bismuth Alloy Zero-Power Reactor
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Topics: Alloys, Safety, Earthquakes, Collisions (Physics), Computer simulation, Coolants, Finite element methods, Leakage, Neutrons, Nuclear fuels
Proceedings Papers

All-Coefficient Adaptive Control System Design for a Space Nuclear Reactor

Qian Ma, Zhitong Yu, Peiwei Sun, Yuwen Jia, Shifa Wu
Proc. ASME. ICONE28, Volume 4: Student Paper Competition, V004T14A043, August 4–6, 2021
Paper No: ICONE28-64459
https://doi.org/10.1115/ICONE28-64459
View Paper titled, All-Coefficient Adaptive Control System Design for a Space Nuclear Reactor
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Topics: Adaptive control, Design, Nuclear reactors, Control systems, Feedback, Fuels, Transfer functions, Ceramics, Control equipment, Dynamic models
Proceedings Papers

Turbulent Flow Characteristics in a Blocked Exterior Subchannel of a Helically Wrapped Rod Bundle

Thien Nguyen, Rodolfo Vaghetto, Yassin Hassan
Proc. ASME. ICONE2020, Volume 3: Student Paper Competition; Thermal-Hydraulics; Verification and Validation, V003T13A029, August 4–5, 2020
Paper No: ICONE2020-16570
https://doi.org/10.1115/ICONE2020-16570
View Paper titled, Turbulent Flow Characteristics in a Blocked Exterior Subchannel of a Helically Wrapped Rod Bundle
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Topics: Fuel rods, Turbulence, Flow (Dynamics), Fuels, Wire, Coolants, Heat transfer, Manufacturing, Cladding systems (Building), Deformation
Proceedings Papers

Finite Element Model to Simulate the Spacer Grid Buckling Characteristics

Youngik Yoo, Joongjin Kim, Kyongbo Eom, Hyeongkoo Kim
Proc. ASME. ICONE2020, Volume 1: Beyond Design Basis; Codes and Standards; Computational Fluid Dynamics (CFD); Decontamination and Decommissioning; Nuclear Fuel and Engineering; Nuclear Plant Engineering, V001T05A002, August 4–5, 2020
Paper No: ICONE2020-16082
https://doi.org/10.1115/ICONE2020-16082
View Paper titled, Finite Element Model to Simulate the Spacer Grid Buckling Characteristics
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Topics: Buckling, Finite element model, Fuel rods, Manufacturing, Mechanical behavior, Nuclear fuels, Compression, Drag (Fluid dynamics), Impact testing, Mechanical properties
Proceedings Papers

Study on the Spacer Grid Dynamic Crush Strength According to Cell Sizes

Jooyoung Ryu, Hangil Woo, Chaeyoung Nam, Youngik Yoo, Namgyu Park, Seungjae Lee
Proc. ASME. ICONE2020, Volume 1: Beyond Design Basis; Codes and Standards; Computational Fluid Dynamics (CFD); Decontamination and Decommissioning; Nuclear Fuel and Engineering; Nuclear Plant Engineering, V001T05A005, August 4–5, 2020
Paper No: ICONE2020-16149
https://doi.org/10.1115/ICONE2020-16149
View Paper titled, Study on the Spacer Grid Dynamic Crush Strength According to Cell Sizes
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Topics: Accidents, Additive manufacturing, Buckling, Cladding systems (Building), Coolants, Deformation, Failure, Flow (Dynamics), Fuel rods, Fuels
Proceedings Papers

Numerical Simulation Method Research on Pellet-Cladding Mechanical Interaction Based on ABAQUS Software

Changbing Tang, Yongjun Jiao, Yuanming Li, Yi Zhou, Kun Zhang
Proc. ASME. ICONE2020, Volume 2: Nuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors, V002T08A036, August 4–5, 2020
Paper No: ICONE2020-16387
https://doi.org/10.1115/ICONE2020-16387
View Paper titled, Numerical Simulation Method Research on Pellet-Cladding Mechanical Interaction Based on ABAQUS Software
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Topics: Cladding systems (Building), Computer simulation, Computer software, Fuel rods, Fuels, Stress, Failure, Pressure, Simulation, Transients (Dynamics)
Proceedings Papers

Preventing Nuclear Fuel Material Adhesion on Glove Box Components Using Nanoparticle Coating

Tomoomi Segawa, Koichi Kawaguchi, Katsunori Ishii, Masahiro Suzuki, Joji Tachihara, Kiyoto Takato, Takatoshi Okita, Hiroshi Satone, Michitaka Suzuki
Proc. ASME. ICONE2020, Volume 1: Beyond Design Basis; Codes and Standards; Computational Fluid Dynamics (CFD); Decontamination and Decommissioning; Nuclear Fuel and Engineering; Nuclear Plant Engineering, V001T05A008, August 4–5, 2020
Paper No: ICONE2020-16215
https://doi.org/10.1115/ICONE2020-16215
View Paper titled, Preventing Nuclear Fuel Material Adhesion on Glove Box Components Using Nanoparticle Coating
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Topics: Adhesion, Coating processes, Coatings, Nanoparticles, Nuclear fuels