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Proc. ASME. ICONE29, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A060, August 8–12, 2022

Paper No: ICONE29-93004

DOI: https://doi.org/10.1115/ICONE29-93004

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Topics: Cladding systems (Building), Fuel rods, Heat transfer, Heat transfer coefficients, Surface roughness

Proceedings Papers

Feasibility Study on Power Ramp Test Under Atmospheric Pressure and Ordinary Temperature

Xiangyu Wei, Wenhua Zhang, Yingchun Zhao

Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A079, August 8–12, 2022

Paper No: ICONE29-93417

DOI: https://doi.org/10.1115/ICONE29-93417

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Topics: Atmospheric pressure, Fuels, Ropes, Temperature, Cladding systems (Building), Stress, Fuel rods, Irradiation (Radiation exposure), Pressure, Sensitivity analysis

Proceedings Papers

Research on the Influence of Degassing on the Release of Fission Gases in PWRs

Yaoxin Ye, Pengtao Fu, Zhijun Li

Proc. ASME. ICONE29, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A008, August 8–12, 2022

Paper No: ICONE29-89461

DOI: https://doi.org/10.1115/ICONE29-89461

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Topics: Failure, Fuels, Gases, Nuclear fission, Pressurized water reactors, Coolants, Nuclear power stations, Cladding systems (Building), Nuclear fuel cycle, Rods

Proceedings Papers

Analysis of the Influence of RCCA Swelling on Rod Falling and Study on Mitigation Measures

Zhipeng Lv, Guoliang Zhang, Changzheng Li, Weichao Liu, Shaofang Lin, Lihong Nie, Zhijun Li, Anlong Zhang

Proc. ASME. ICONE29, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A067, August 8–12, 2022

Paper No: ICONE29-93095

DOI: https://doi.org/10.1115/ICONE29-93095

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Topics: Absorption, Cladding systems (Building), Deformation, Design, Irradiation (Radiation exposure), Neutrons, Pressurized water reactors, Rods, Safety, Shock absorbers

Proceedings Papers

A Bi-Layered Three-Dimensional Mechanical Modeling of the Cladding and Its Creep Deformation Analysis

Ming Zhang, Jinggang Li, Xiaohan Liu, Yong Lu, Yanan Zhu

Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A004, August 8–12, 2022

Paper No: ICONE29-88944

DOI: https://doi.org/10.1115/ICONE29-88944

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Topics: Cladding systems (Building), Collapse, Creep, Modeling

Proceedings Papers

Mechanical Performance Assessment of Independently-Developed Zirconium Alloy Under RIA Condition

Jie Wang, Yang Wang, Jun Wei, Yongjun Deng

Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A015, August 8–12, 2022

Paper No: ICONE29-90521

DOI: https://doi.org/10.1115/ICONE29-90521

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Topics: Cladding systems (Building), Ductility, Equipment performance, Hydrogen, Zirconium alloys, Zirconium, Accidents, Failure, Fracture (Process), Light water reactors

Proceedings Papers

Study of Pre-Oxidization Law and Fretting Wear Resistance of CZ2 Alloy Cladding

Guocheng Sun, Shi Lin, Xu Wang, Liutao Chen

Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A088, August 8–12, 2022

Paper No: ICONE29-93804

DOI: https://doi.org/10.1115/ICONE29-93804

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Topics: Alloys, Cladding systems (Building), Wear, Wear resistance

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

DOI: https://doi.org/10.1115/ICONE29-89580

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Topics: Accidents, Cladding systems (Building), Nuclear fuels, Zirconium alloys

Proceedings Papers

Hydrogenation of Zircaloy-4 in a Defective Fuel Pellet for Pressurized Water Reactors

Doctor Enivweru, Qingyu Wang, Abiodun Ayodeji, John Njoroge

Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A021, August 8–12, 2022

Paper No: ICONE29-90736

DOI: https://doi.org/10.1115/ICONE29-90736

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Topics: Corrosion, Fuels, Hydrogen embrittlement, Pressurized water reactors, Cladding systems (Building), Hydrogen, Temperature, Accidents, Boundary-value problems, Coolants

Proceedings Papers

Microstructual and Micro-Chemical Analysis of Zr Cladding Alloys on Corrosion and Creep Properties

Qing Yang Lv, Libin Zhang, Minli Chen, Changyuan Gao, Yang Xu, Liutao Chen, Jun Tan

Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A086, August 8–12, 2022

Paper No: ICONE29-93770

DOI: https://doi.org/10.1115/ICONE29-93770

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Topics: Alloys, Annealing, Cladding systems (Building), Corrosion, Creep, Tin, Zirconium

Proceedings Papers

Design of Radiation Damage Monitoring Scheme for Materials in China Experimental Fast Reactor

Hu Ziao, Chen Xiao-xian, Chen Xiao-liang

Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A010, August 8–12, 2022

Paper No: ICONE29-90146

DOI: https://doi.org/10.1115/ICONE29-90146

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Topics: China, Damage, Design, Fast neutron reactors, Irradiation (Radiation exposure), Neutron flux, Radiation damage, Sensors, Neutrons, Cladding systems (Building)

Proceedings Papers

A Method to Evaluate Defect Size of Failed Fuel Rods in CGN 1000MWe PWRs

Pengtao Fu, Zhijun Li

Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A063, August 8–12, 2022

Paper No: ICONE29-92788

DOI: https://doi.org/10.1115/ICONE29-92788

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Topics: Failure, Fuel rods, Fuels, Nuclear fission, Pressurized water reactors, Cladding systems (Building), Rods, Irradiation (Radiation exposure)

Proceedings Papers

Applying Machine Learning to Improve BOA Analysis of CIPS/CILC

Jun Liao, Alexander Mace, Guoqiang Wang, Jesse S. Fisher

Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A095, August 8–12, 2022

Paper No: ICONE29-94480

DOI: https://doi.org/10.1115/ICONE29-94480

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Topics: Machine learning, Boron, Corrosion, Fuels, Nuclear power stations, Algorithms, Calibration, Chemistry, Cladding systems (Building), Computers

Proceedings Papers

Potential Crud Related Margin Gains With Chromium Coated Zirconium Cladding

William A. Byers, Guoqiang Wang

Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A094, August 8–12, 2022

Paper No: ICONE29-94477

DOI: https://doi.org/10.1115/ICONE29-94477

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Topics: Cladding systems (Building), Zirconium, Corrosion, Coating processes, Coatings, Fuels, Pressurized water reactors, Accidents, Boiling, Boron

Proceedings Papers

Comparative Machine Learning Study for Estimating Peak Cladding Temperature in AP1000 Under LOFW

Merouane Najar, He Wang

Proc. ASME. ICONE29, Volume 5: Nuclear Safety, Security, and Cyber Security, V005T05A022, August 8–12, 2022

Paper No: ICONE29-91516

DOI: https://doi.org/10.1115/ICONE29-91516

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Topics: Cladding systems (Building), Machine learning, Temperature, Algorithms, Uncertainty quantification, Accidents, Safety, Uncertainty, Databases, Errors

Proceedings Papers

Research on Fretting Wear of Grid and Cladding Tube Under Simulated Primary Circuit Environment of Pressurized Water Reactor

Tingting Liu, Kun Li, Wenhui Ma, Yuxiang Zhang, Minli Chen, Xiaohang Wu

Proc. ASME. ICONE29, Volume 7A: Thermal-Hydraulics and Safety Analysis, V07AT07A044, August 8–12, 2022

Paper No: ICONE29-91561

DOI: https://doi.org/10.1115/ICONE29-91561

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Topics: Circuits, Cladding systems (Building), Pressurized water reactors, Wear

Proceedings Papers

Evaluation of the Parameter Importance Changes Over Time for Nuclear Reactor Transients

Qingwen Xiong, Gongle Song, Peng Du, Tao Huang, Jian Deng

Proc. ASME. ICONE29, Volume 7A: Thermal-Hydraulics and Safety Analysis, V07AT07A006, August 8–12, 2022

Paper No: ICONE29-89017

DOI: https://doi.org/10.1115/ICONE29-89017

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Topics: Accidents, Coolants, Nuclear reactors, Sensitivity analysis, Transients (Dynamics), Cladding systems (Building), Nuclear reactor accidents, Temperature, B-splines, Regression analysis

Proceedings Papers

A Chinese 300MWe Two-Loop PWR NPP LBLOCA Analysis Based on the Deterministic Realistic Hybrid Methodology

Yuhan Li, Bo Kuang

Proc. ASME. ICONE29, Volume 7B: Thermal-Hydraulics and Safety Analysis, V07BT07A009, August 8–12, 2022

Paper No: ICONE29-92431

DOI: https://doi.org/10.1115/ICONE29-92431

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Topics: Nuclear power stations, Pressurized water reactors, Safety, Accidents, Life extension, Uncertainty, China, Cladding systems (Building), Coolants, Design

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Multiphysics Analysis of Fuel Performance and Tritium Migration in FeCrAl and Cr-Coated Zircalloy Cladding Under PWR Normal Operating and Transient Conditions

Multiphysics Analysis of UN Fuel Performance With a Two-Layered SiC Cladding Under Multiple Operating Conditions in a Light Water Reactor

Study on the Influence of Roughness on Fuel Rod Gap Heat Transfer

Feasibility Study on Power Ramp Test Under Atmospheric Pressure and Ordinary Temperature

Research on the Influence of Degassing on the Release of Fission Gases in PWRs

Analysis of the Influence of RCCA Swelling on Rod Falling and Study on Mitigation Measures

A Bi-Layered Three-Dimensional Mechanical Modeling of the Cladding and Its Creep Deformation Analysis

Mechanical Performance Assessment of Independently-Developed Zirconium Alloy Under RIA Condition

Study of Pre-Oxidization Law and Fretting Wear Resistance of CZ2 Alloy Cladding

Analysis of Hydrogenation Properties of Nuclear Fuel Zirconium Alloy Cladding

Hydrogenation of Zircaloy-4 in a Defective Fuel Pellet for Pressurized Water Reactors

Microstructual and Micro-Chemical Analysis of Zr Cladding Alloys on Corrosion and Creep Properties

Design of Radiation Damage Monitoring Scheme for Materials in China Experimental Fast Reactor

A Method to Evaluate Defect Size of Failed Fuel Rods in CGN 1000MWe PWRs

Applying Machine Learning to Improve BOA Analysis of CIPS/CILC

Potential Crud Related Margin Gains With Chromium Coated Zirconium Cladding

Comparative Machine Learning Study for Estimating Peak Cladding Temperature in AP1000 Under LOFW

Research on Fretting Wear of Grid and Cladding Tube Under Simulated Primary Circuit Environment of Pressurized Water Reactor

Evaluation of the Parameter Importance Changes Over Time for Nuclear Reactor Transients

A Chinese 300MWe Two-Loop PWR NPP LBLOCA Analysis Based on the Deterministic Realistic Hybrid Methodology

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