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Proceedings Papers

Effects of Stoichiometry and High-Temperature Annealing on Zirconium Carbide Coating Layer in TRISO Particles

Xinyu Cheng, Rongzheng Liu, Bing Liu, Xu Yang, Malin Liu, Jiaxing Chang, Youlin Shao

Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A066, August 8–12, 2022

Paper No: ICONE29-92858

DOI: https://doi.org/10.1115/ICONE29-92858

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Topics: Annealing, Coatings, Fuels, High temperature, Particulate matter, Stoichiometry, Very high temperature reactors, Zirconium

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 on Out-Pile Performance of CZ Zirconium Alloy Guide Tube

Changyuan Gao, Lin Shi, Guoliang Zhang, Yang Xu, Minli Chen, Liutao Chen, Jun Tan

Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A089, August 8–12, 2022

Paper No: ICONE29-93816

DOI: https://doi.org/10.1115/ICONE29-93816

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Topics: Corrosion, Creep, Zirconium alloys, Alloys, Zirconium, Corrosion resistance, Stress, Temperature, Mechanical testing, Particulate matter

Proceedings Papers

High Temperature Oxidation Kinetics of Zr-Sn-Nb Alloy and the Effect of Its Oxide Film Growth On Corrosion Resistance

Wanqian Zhao

Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A083, August 8–12, 2022

Paper No: ICONE29-93520

DOI: https://doi.org/10.1115/ICONE29-93520

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Topics: Alloys, Corrosion resistance, High temperature, Oxidation, Tin, Zirconium, Zirconium alloys

Proceedings Papers

Investigation of Swelling Behaviors of U-10Zr Metallic Fuel in the Low Temperature Regime via a Combined Thermo-Mechanical and Rate Theory Analysis

Zhengyu Qian, Di Yun

Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A053, August 8–12, 2022

Paper No: ICONE29-92285

DOI: https://doi.org/10.1115/ICONE29-92285

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Topics: Fuels, Low temperature, Thermomechanics, Uranium, Zirconium

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

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

DOI: https://doi.org/10.1115/ICONE29-93196

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Topics: Composite materials, Fittings, Metals, Sewage, Temperature, Water, Zirconium

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

High-Temperature Deformation Constitutive Relationship of Zr-Sn-Nb Alloy for Nuclear Power

Yingqi Gao, Ben Wang, Jianguo Cao, Qianqian Luo, Yuan Cao, Zhihao Zhang, Lian Wang, Bo Gao

Proc. ASME. ICONE29, Volume 10: Advanced Methods of Manufacturing for Nuclear Reactors and Components, V010T10A022, August 8–12, 2022

Paper No: ICONE29-92123

DOI: https://doi.org/10.1115/ICONE29-92123

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Topics: Alloys, Constitutive equations, Deformation, High temperature, Nuclear power, Temperature, Tin, Zirconium

Proceedings Papers

Microstructure, Texture and Mechanical Properties in Different Deformation Regions of the Compressed Zr-4 Alloy With Lamellar Structure

Jie Ren, Geping Li, Fusen Yuan, Ben Wang, Fuzhou Han, Muhammad Ali, Yingdong Zhang, Wenbin Guo, Bo Gao

Proc. ASME. ICONE29, Volume 10: Advanced Methods of Manufacturing for Nuclear Reactors and Components, V010T10A027, August 8–12, 2022

Paper No: ICONE29-92283

DOI: https://doi.org/10.1115/ICONE29-92283

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Topics: Alloys, Deformation, Mechanical properties, Recrystallization, Texture (Materials), Zirconium

Proceedings Papers

The Research on Welding Procedure and Performance of Zr-3 Thick Plate

Yu Gao, Xiaoru Liang, Yuxin Wang, Lifeng Guo

Proc. ASME. ICONE29, Volume 10: Advanced Methods of Manufacturing for Nuclear Reactors and Components, V010T10A021, August 8–12, 2022

Paper No: ICONE29-92037

DOI: https://doi.org/10.1115/ICONE29-92037

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Topics: Corrosion resistance, Heat treating (Metalworking), Mechanical properties, Welding, Zirconium

Proceedings Papers

Die Design and Process Study of Zr-4 Alloy Profile Extrusion

Peng Qi, Bo Gao, Zhihao Zhang, Jianming Yin

Proc. ASME. ICONE29, Volume 10: Advanced Methods of Manufacturing for Nuclear Reactors and Components, V010T10A041, August 8–12, 2022

Paper No: ICONE29-92961

DOI: https://doi.org/10.1115/ICONE29-92961

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Topics: Alloys, Computer simulation, Design, Extruding, Zirconium, Zirconium alloys

Proceedings Papers

Experimental Investigation on the Formation and Break-Up of Gas Stratification in the COTHYD Facility

Yuchen Zhang, Yuzhou Lu, Xiangyu Yun, Huiyong Zhang

Proc. ASME. ICONE29, Volume 7A: Thermal-Hydraulics and Safety Analysis, V07AT07A068, August 8–12, 2022

Paper No: ICONE29-92162

DOI: https://doi.org/10.1115/ICONE29-92162

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Topics: Accidents, China, Containment, Erosion, Helium, Hydrogen, Nuclear power, Pressurized water reactors, Sprays, Steam

Proceedings Papers

Preliminary Prediction of Young’s Modulus and Thermal Conductivity of Porous U-50 wt.% Zr Alloy: A Molecular Dynamic and Semi-Empirical Study

Mengke Cai, Tenglong Cong, Hanyang Gu

Proc. ASME. ICONE29, Volume 15: Student Paper Competition, V015T16A048, August 8–12, 2022

Paper No: ICONE29-91602

DOI: https://doi.org/10.1115/ICONE29-91602

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Topics: Molecular dynamics, Porosity, Thermal conductivity, Young's modulus, Zirconium, Zirconium alloys

Proceedings Papers

A Steady-State Analysis of U-Pu-Zr Metallic Fuel Performance on Constituent Redistribution by Multiphysics Modeling

Rong Liu, Shengyu Liu, Huiyun Han, Liwen Yang

Proc. ASME. ICONE29, Volume 15: Student Paper Competition, V015T16A093, August 8–12, 2022

Paper No: ICONE29-92447

DOI: https://doi.org/10.1115/ICONE29-92447

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Topics: Fuels, Modeling, Steady state, Zirconium

Proceedings Papers

Corrosion Behavior of Zr-0.75Sn-0.35Fe-0.15Cr- x Nb Alloys in Oxygen-Containing Super-Heated Steam at 400 °C

Meiyi Yao, Shitong Xu, Wen Pei, Lijuan Hu, Xiaodong Lin, Yaoping Xie, Jianchao Peng, Xue Liang, Bangxin Zhou

Proc. ASME. ICONE29, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A009, August 8–12, 2022

Paper No: ICONE29-91231

DOI: https://doi.org/10.1115/ICONE29-91231

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Topics: Corrosion, Niobium alloys, Oxygen, Steam, Superheating, Zirconium, Zirconium alloys

Proceedings Papers

Research on Dimensionless Analysis Method of Scale Effects for Molten Pool Experiments

Fengyang Quan, Wei Li, Zikun Zhao, Xiao Zeng, Yong Guo, Yidan Yuan

Proc. ASME. ICONE28, Volume 2: Nuclear Fuels, Research, and Fuel Cycle; Nuclear Codes and Standards; Thermal-Hydraulics, V002T07A024, August 4–6, 2021

Paper No: ICONE28-64739

DOI: https://doi.org/10.1115/ICONE28-64739

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Topics: Accidents, Cladding systems (Building), Coolants, Cooling, Dimensional analysis, Engineering prototypes, Failure, Floods, Fuels, Heat flux

Proceedings Papers

Experimental Study on Heat Transfer Characteristics of Water Injection on Molten Pool With Low Mass Fraction of Zirconium

Zongyang Li, Huajian Chang, Fangfang Fang, Kun Han, Botao Hao, Lian Chen

Proc. ASME. ICONE28, Volume 4: Student Paper Competition, V004T14A005, August 4–6, 2021

Paper No: ICONE28-62115

DOI: https://doi.org/10.1115/ICONE28-62115

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Topics: Heat transfer, Underground injection, Zirconium

Proceedings Papers

Modeling of Low-Temperature Reduction of Metal Oxide in Hydrogen Treatment System for Severe Accidents in Nuclear Power Plants

Kotaro Nakamura, Masashi Tanabe, Satoru Abe, Takashi Mawatari, Takao Nakagaki

Proc. ASME. ICONE2020, Volume 3: Student Paper Competition; Thermal-Hydraulics; Verification and Validation, V003T12A029, August 4–5, 2020

Paper No: ICONE2020-16450

DOI: https://doi.org/10.1115/ICONE2020-16450

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Topics: Accidents, Copper, Hydrogen, Low temperature, Metals, Modeling, Nuclear power stations, Oxidation, Explosions, Water vapor

Proceedings Papers

Uncertainty Quantification for the Development of Mechanistic Hydride Behavior Model for Spent Fuel Cladding Storage and Transportation

Edward M. Duchnowski, Seokbin Seo, Nicholas R. Brown

Proc. ASME. ICONE2020, Volume 3: Student Paper Competition; Thermal-Hydraulics; Verification and Validation, V003T12A046, August 4–5, 2020

Paper No: ICONE2020-16812

DOI: https://doi.org/10.1115/ICONE2020-16812

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Topics: Cladding systems (Building), Spent nuclear fuels, Storage, Transportation systems, Uncertainty quantification, Hydrogen, Diffusion (Physics), Fuels, Temperature profiles, Uncertainty

NARROW

Effects of Stoichiometry and High-Temperature Annealing on Zirconium Carbide Coating Layer in TRISO Particles

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

Study on Out-Pile Performance of CZ Zirconium Alloy Guide Tube

High Temperature Oxidation Kinetics of Zr-Sn-Nb Alloy and the Effect of Its Oxide Film Growth On Corrosion Resistance

Investigation of Swelling Behaviors of U-10Zr Metallic Fuel in the Low Temperature Regime via a Combined Thermo-Mechanical and Rate Theory Analysis

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

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

Potential Crud Related Margin Gains With Chromium Coated Zirconium Cladding

High-Temperature Deformation Constitutive Relationship of Zr-Sn-Nb Alloy for Nuclear Power

Microstructure, Texture and Mechanical Properties in Different Deformation Regions of the Compressed Zr-4 Alloy With Lamellar Structure

The Research on Welding Procedure and Performance of Zr-3 Thick Plate

Die Design and Process Study of Zr-4 Alloy Profile Extrusion

Experimental Investigation on the Formation and Break-Up of Gas Stratification in the COTHYD Facility

Preliminary Prediction of Young’s Modulus and Thermal Conductivity of Porous U-50 wt.% Zr Alloy: A Molecular Dynamic and Semi-Empirical Study

A Steady-State Analysis of U-Pu-Zr Metallic Fuel Performance on Constituent Redistribution by Multiphysics Modeling

Corrosion Behavior of Zr-0.75Sn-0.35Fe-0.15Cr- x Nb Alloys in Oxygen-Containing Super-Heated Steam at 400 °C

Research on Dimensionless Analysis Method of Scale Effects for Molten Pool Experiments

Experimental Study on Heat Transfer Characteristics of Water Injection on Molten Pool With Low Mass Fraction of Zirconium

Modeling of Low-Temperature Reduction of Metal Oxide in Hydrogen Treatment System for Severe Accidents in Nuclear Power Plants

Uncertainty Quantification for the Development of Mechanistic Hydride Behavior Model for Spent Fuel Cladding Storage and Transportation

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