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Proceedings Papers

Crack Propagation Analysis of Dissimilar Metal Weld for Steam Generator Nozzle Safety End

Shuang Qi, Wenxin Xiang, Ping Huang, Fangmao Ning, Minyu Fan, Lei Qi, Mingya Chen, Jun Xu
Proc. ASME. ICONE29, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A074, August 8–12, 2022
Paper No: ICONE29-93289
https://doi.org/10.1115/ICONE29-93289
View Paper titled, Crack Propagation Analysis of Dissimilar Metal Weld for Steam Generator Nozzle Safety End
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Topics: Boilers, Crack propagation, Metals, Nozzles, Safety
Proceedings Papers

An Insulation Structure With Noise Reduction Function

Zhang Yicheng, Bian Pengfei, Zhang Kai
Proc. ASME. ICONE29, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A069, August 8–12, 2022
Paper No: ICONE29-93144
https://doi.org/10.1115/ICONE29-93144
View Paper titled, An Insulation Structure With Noise Reduction Function
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Topics: Acoustics, Insulation, Noise control, Thermal insulation, Nuclear power, Acoustical materials, Glass, Pipelines, Damping, Density
Proceedings Papers

Research Progress of Neutron Shielding Materials

Bing Chang, Saisai Li, Minghui Li, Ruoyu Chen
Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A050, August 8–12, 2022
Paper No: ICONE29-92210
https://doi.org/10.1115/ICONE29-92210
View Paper titled, Research Progress of Neutron Shielding Materials
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Topics: Metals, Neutrons, Polymers
Proceedings Papers

Numerical Study of the Effect of δ-Ferrite on Crack-Tip Mechanical Field

Yule Wu, Lefu Zhang
Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A060, August 8–12, 2022
Paper No: ICONE29-92656
https://doi.org/10.1115/ICONE29-92656
View Paper titled, Numerical Study of the Effect of δ-Ferrite on Crack-Tip Mechanical Field
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Topics: Ferrites (Magnetic materials), Fracture (Materials), Stress, Cracking (Materials), Fracture (Process), Embrittlement, Finite element analysis, Finite element methods, Finite element model, High temperature
Proceedings Papers

Study on Synthesis of the Organophosphorus Functionalized MCM-41 And its Adsorption Property for Dy(III)

Cong Mao, Hongji Sang, Jiawei Zheng, Yan Wu
Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A077, August 8–12, 2022
Paper No: ICONE29-93196
https://doi.org/10.1115/ICONE29-93196
View Paper titled, Study on Synthesis of the Organophosphorus Functionalized MCM-41 And its Adsorption Property for Dy(III)
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Topics: Composite materials, Fittings, Metals, Sewage, Temperature, Water, Zirconium
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

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
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

Analysis of Different Requirements of Dissimilar Metal Joint Welding Procedure Qualification Between RCC-M and ASME BPVC

Wang Pei, Chen Dongxu, Yang Shumin
Proc. ASME. ICONE29, Volume 6: Nuclear Codes, Standards, Licensing, and Regulatory Issues, V006T06A007, August 8–12, 2022
Paper No: ICONE29-91363
https://doi.org/10.1115/ICONE29-91363
View Paper titled, Analysis of Different Requirements of Dissimilar Metal Joint Welding Procedure Qualification Between RCC-M and ASME BPVC
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Topics: ASME Boiler and Pressure Vessel Code, Boilers, Metals, Welding
Proceedings Papers

Research on GIL Fault Diagnosis and Location Method Based on Partial Discharge and Vibration Monitoring

Sen Liu
Proc. ASME. ICONE29, Volume 12: Innovative and Smart Nuclear Power Plant Design, V012T12A020, August 8–12, 2022
Paper No: ICONE29-92174
https://doi.org/10.1115/ICONE29-92174
View Paper titled, Research on GIL Fault Diagnosis and Location Method Based on Partial Discharge and Vibration Monitoring
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Topics: Fault diagnosis, Vibration, Signals, Metals, Transmission lines, Eigenvalues, Sensors, Simulation, Economics , Fault location (Engineering)
Proceedings Papers

Development of Drift Flux-Type Correlations Considering Bubble Induced Turbulence in Vertical Gas-Liquid Metal Two-Phase Flow

Di Wang, Ren Liang, Zhikang Lin, Yong Ouyang, Yonggang Shen, Xianghui Lu, Suizhen Qiu
Proc. ASME. ICONE29, Volume 7B: Thermal-Hydraulics and Safety Analysis, V07BT07A033, August 8–12, 2022
Paper No: ICONE29-93078
https://doi.org/10.1115/ICONE29-93078
View Paper titled, Development of Drift Flux-Type Correlations Considering Bubble Induced Turbulence in Vertical Gas-Liquid Metal Two-Phase Flow
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Topics: Bubbles, Metals, Turbulence, Two-phase flow
Proceedings Papers

Modeling of Irradiation-Induced Thermo-Mechanical Coupling Behavior in Metal Matrix Microencapsulated Fuel

Hongyang Wei, Fawen Zhu, Jun Ru, Haoyu Wang, Jing Zhang, Hua Li, Yun Li, Chunlan Huang, Yuanming Li, Shurong Ding
Proc. ASME. ICONE28, Volume 2: Nuclear Fuels, Research, and Fuel Cycle; Nuclear Codes and Standards; Thermal-Hydraulics, V002T05A016, August 4–6, 2021
Paper No: ICONE28-65563
https://doi.org/10.1115/ICONE28-65563
View Paper titled, Modeling of Irradiation-Induced Thermo-Mechanical Coupling Behavior in Metal Matrix Microencapsulated Fuel
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Topics: Finite element analysis, Fuels, Irradiation (Radiation exposure), Metals, Modeling, Thermomechanics
Proceedings Papers

Spreading Behavior of Molten Metal on Flat Plate in a Shallow Water Pool

Yasunori Yamamoto, Tomomasa Ito, Kyosuke Nihashi, Shuichiro Miwa
Proc. ASME. ICONE28, Volume 2: Nuclear Fuels, Research, and Fuel Cycle; Nuclear Codes and Standards; Thermal-Hydraulics, V002T07A020, August 4–6, 2021
Paper No: ICONE28-64614
https://doi.org/10.1115/ICONE28-64614
View Paper titled, Spreading Behavior of Molten Metal on Flat Plate in a Shallow Water Pool
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Topics: Flat plates, Metals, Water
Proceedings Papers

Investigation on Solidification Behavior of Deposited Metal by GTAW With ERNiCrFe-13 Wire

Xiao Guo, Kai Xu, Xiaochun Lv, Peiyin Chen, Bo Chen, Shubin Huo
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, V003T10A001, August 4–6, 2021
Paper No: ICONE28-63770
https://doi.org/10.1115/ICONE28-63770
View Paper titled, Investigation on Solidification Behavior of Deposited Metal by GTAW With ERNiCrFe-13 Wire
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Topics: Gas tungsten arc welding, Metals, Solidification, Wire, Temperature, Cracking (Materials), Fracture (Process), Differential scanning calorimetry, Ductility, Lasers
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

Experimental Study for Evaluation of Spreading Behavior of Free-Falling Molten Core With Floor Impingement

Tomomasa Ito, Yuta Watanabe, Yasunori Yamamoto, Nassim Sahboun, Shuichiro Miwa
Proc. ASME. ICONE2020, Volume 3: Student Paper Competition; Thermal-Hydraulics; Verification and Validation, V003T12A054, August 4–5, 2020
Paper No: ICONE2020-16942
https://doi.org/10.1115/ICONE2020-16942
View Paper titled, Experimental Study for Evaluation of Spreading Behavior of Free-Falling Molten Core With Floor Impingement
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Topics: Accidents, Dimensionless numbers, Errors, Metals, Nuclear decommissioning, Tin, Uncertainty
Proceedings Papers

Friction Factor Correlation for Molten Metals Flow in a 3-Rod Bundle in Cylindrical Shroud, With Smooth and Scalloped Inner Wall

Timothy Schriener, Mohamed S. El-Genk
Proc. ASME. ICONE2020, Volume 3: Student Paper Competition; Thermal-Hydraulics; Verification and Validation, V003T13A017, August 4–5, 2020
Paper No: ICONE2020-16239
https://doi.org/10.1115/ICONE2020-16239
View Paper titled, Friction Factor Correlation for Molten Metals Flow in a 3-Rod Bundle in Cylindrical Shroud, With Smooth and Scalloped Inner Wall
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Topics: Computational fluid dynamics, Flow (Dynamics), Friction, Metals, Pressure
Proceedings Papers

A Laser Decontamination Technology for Radioactive Contaminated Metals

Zhao Wan, Cao Junjie, Wang Shuai, Chen Xumin, Zhang Yongling
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, V001T04A002, August 4–5, 2020
Paper No: ICONE2020-16070
https://doi.org/10.1115/ICONE2020-16070
View Paper titled, A Laser Decontamination Technology for Radioactive Contaminated Metals
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Topics: Decontamination, Laser ablation, Lasers, Metals
Proceedings Papers

Analysis of Transient Corium Pool Structure in the Lower Plenum of Reactor Vessel

Liang Chen, Hua Pang, Ximing Xie, Lei Zhong, Rong Cai
Proc. ASME. ICONE2020, Volume 2: Nuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors, V002T08A041, August 4–5, 2020
Paper No: ICONE2020-16470
https://doi.org/10.1115/ICONE2020-16470
View Paper titled, Analysis of Transient Corium Pool Structure in the Lower Plenum of Reactor Vessel
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Topics: Accidents, Reactor vessels, Transients (Dynamics), Vessels, Density, Heat flux, Heavy metals, China, Coolants, Critical heat flux
Proceedings Papers

Effects of Pre-Crack Depth and Hydrogen Absorption on the Failure Strain of Zircaloy-4 Cladding Tubes Under Biaxial Strain Conditions

Feng Li, Takeshi Mihara, Yutaka Udagawa, Masaki Amaya
Proc. ASME. ICONE2020, Volume 2: Nuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors, V002T08A052, August 4–5, 2020
Paper No: ICONE2020-16738
https://doi.org/10.1115/ICONE2020-16738
View Paper titled, Effects of Pre-Crack Depth and Hydrogen Absorption on the Failure Strain of Zircaloy-4 Cladding Tubes Under Biaxial Strain Conditions
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Topics: Absorption, Cladding systems (Building), Failure, Fracture (Materials), Hydrogen, Heat treating (Metalworking), Accidents, Fuels, Manufacturing, Metals
Proceedings Papers

Evaluation of Irradiation Embrittlement of the Weld Metals in the Chinese RPV

Yupeng Cao, Yinbiao He, Yifeng Huang, Binxi Wang, Yan Yu, Hui Li, Hu Hui
Proc. ASME. ICONE2020, Volume 2: Nuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors, V002T09A003, August 4–5, 2020
Paper No: ICONE2020-16261
https://doi.org/10.1115/ICONE2020-16261
View Paper titled, Evaluation of Irradiation Embrittlement of the Weld Metals in the Chinese RPV
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Topics: Embrittlement, Irradiation (Radiation exposure), Metals, Forging, Mechanical properties, China, Damage, Design, Fluence (Radiation measurement), Fracture toughness