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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