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Proceedings Papers

Ways to Solve the Safe Operation of VVER-1000 Reactors in Case of Loss of Original Rod Cluster Control Assemblies Supply

Oleksandr Mazurok, Valeriy Zuyok, Vadym Ivanov, Mykhaylo Tretyakov
Proc. ASME. ICONE31, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A018, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-134916
https://doi.org/10.1115/ICONE31-134916
View Paper titled, Ways to Solve the Safe Operation of VVER-1000 Reactors in Case of Loss of Original Rod Cluster Control Assemblies Supply
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Topics: Absorption, Boron, Cladding systems (Building), Density, Dysprosium, Europium, Fuels, Hafnium, Neutrons, Nuclear power stations
Proceedings Papers

Preliminary Investigation on Burst Behaviors of Zr-Based Cladding Under Simulated LOCA Conditions

Zhengang Duan, Bo Yuan, Qinglong Wen, Kang Chen
Proc. ASME. ICONE31, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A020, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-134397
https://doi.org/10.1115/ICONE31-134397
View Paper titled, Preliminary Investigation on Burst Behaviors of Zr-Based Cladding Under Simulated LOCA Conditions
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Topics: Accidents, Cladding systems (Building), Fuels, Loss of coolant accidents, Zirconium
Proceedings Papers

The SPIZWURZ Project - Experimental and Modeling Approaches of Hydrogen in Cladding Tubes Under Dry Storage Conditions

Sarah Weick, Michel Herm, Mirco Grosse, Robert Kilger, Conrado Rössger, Martin Steinbrueck, Juri Stuckert
Proc. ASME. ICONE31, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A064, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-136905
https://doi.org/10.1115/ICONE31-136905
View Paper titled, The SPIZWURZ Project - Experimental and Modeling Approaches of Hydrogen in Cladding Tubes Under Dry Storage Conditions
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Topics: Cladding systems (Building), Hydrogen, Modeling, Storage
Proceedings Papers

Investigation on Oxidation Behaviors of FeCrAl Alloy Cladding Under the Simulated LOCA Conditions

Kang Chen, Zhengang Duan, Qinglong Wen, Ruiqian Zhang
Proc. ASME. ICONE31, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A047, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-135966
https://doi.org/10.1115/ICONE31-135966
View Paper titled, Investigation on Oxidation Behaviors of FeCrAl Alloy Cladding Under the Simulated LOCA Conditions
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Topics: Alloys, Cladding systems (Building), Loss of coolant accidents, Oxidation
Proceedings Papers

Monte Carlo Simulation of Response of Beta-Delayed Neutron Inspection System for Fuel Cladding Damage

Weihua Zhang, Liguo Zhang, Jianzhu Cao
Proc. ASME. ICONE31, Volume 5: Nuclear Safety, Security, and Cyber Security; Nuclear Codes, Standards, Licensing, and Regulatory Issues, V005T05A010, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-134218
https://doi.org/10.1115/ICONE31-134218
View Paper titled, Monte Carlo Simulation of Response of Beta-Delayed Neutron Inspection System for Fuel Cladding Damage
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Topics: Cladding systems (Building), Damage, Fuels, Inspection, Neutrons, Simulation
Proceedings Papers

Study on NUREG-2215 Regulatory Condition for Reflooding of the Previously Dried High Burnup Fuel Is Not Allowable During Dry Storage

Ting-Yi Liao, Yi-Fan Tseng, Kuan-Che Lan, Wan-June Chiu, Hsiao-Ming Tung
Proc. ASME. ICONE31, Volume 5: Nuclear Safety, Security, and Cyber Security; Nuclear Codes, Standards, Licensing, and Regulatory Issues, V005T06A007, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-135819
https://doi.org/10.1115/ICONE31-135819
View Paper titled, Study on NUREG-2215 Regulatory Condition for Reflooding of the Previously Dried High Burnup Fuel Is Not Allowable During Dry Storage
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Topics: Cladding systems (Building), Fuels, Storage
Proceedings Papers

Study on Thermal-Hydraulic Characteristics of Horizontal Lead-Based Reactor Whole Core

Minyang Gui, Di Wu, Hangyuan Zhang, Senmiao Zhang, Hui Cheng
Proc. ASME. ICONE31, Volume 6: Thermal-Hydraulics and Safety Analysis, V006T07A106, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-136580
https://doi.org/10.1115/ICONE31-136580
View Paper titled, Study on Thermal-Hydraulic Characteristics of Horizontal Lead-Based Reactor Whole Core
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Topics: Cladding systems (Building), Coolants, Fast neutron reactors, Flow (Dynamics), Gravity (Force), Manufacturing, Nuclear power stations, Power density, Safety, Temperature
Proceedings Papers

Investigation on Development of New Mechanistic Model for Post Dryout Heat Transfer

Zihan Xia, Xu Cheng
Proc. ASME. ICONE31, Volume 6: Thermal-Hydraulics and Safety Analysis, V006T07A060, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-135118
https://doi.org/10.1115/ICONE31-135118
View Paper titled, Investigation on Development of New Mechanistic Model for Post Dryout Heat Transfer
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Topics: Drops, Heat transfer, Vapors, Loss of coolant accidents, Wall temperature, Cladding systems (Building), Computational fluid dynamics, Evaporation, Flow (Dynamics), Fuels
Proceedings Papers

Effect of Corrosion Behavior on the Heat Transfer Performance of Fuel Cladding in Lead-Cooled Fast Reactors

Wenpei Feng, Shangdong Yang, Hongxing Yu, Xingqing Lu, Xue Zhang, Zhixing Gu
Proc. ASME. ICONE31, Volume 6: Thermal-Hydraulics and Safety Analysis, V006T07A040, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-134758
https://doi.org/10.1115/ICONE31-134758
View Paper titled, Effect of Corrosion Behavior on the Heat Transfer Performance of Fuel Cladding in Lead-Cooled Fast Reactors
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Topics: Cladding systems (Building), Corrosion, Fast neutron reactors, Fuels, Heat transfer
Proceedings Papers

Numerical Simulation Study on Cladding Blister of Parallel Fuel Plates Under Subcooled Boiling

Kexin Liu, Jianjun Xu, Ming Ding, Xiaxin Cao
Proc. ASME. ICONE31, Volume 7: Computational Fluid Dynamics (CFD) and Applications, V007T08A012, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-134729
https://doi.org/10.1115/ICONE31-134729
View Paper titled, Numerical Simulation Study on Cladding Blister of Parallel Fuel Plates Under Subcooled Boiling
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Topics: Boiling, Cladding systems (Building), Computer simulation, Fuels, Plates (structures), Subcooling
Proceedings Papers

Surrogate Modeling Advancements in Nuclear Fuel Engineering: Bridging the Gap Between Accuracy and Efficiency

Salvatore Angelo Cancemi, Michela Angelucci, Rosa Lo Frano, Sandro Paci
Proc. ASME. ICONE31, Volume 11: Student Paper Competition, V011T15A070, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-135798
https://doi.org/10.1115/ICONE31-135798
View Paper titled, Surrogate Modeling Advancements in Nuclear Fuel Engineering: Bridging the Gap Between Accuracy and Efficiency
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Topics: Metamodeling, Nuclear fuels, Artificial neural networks, Cladding systems (Building), Simulation, Temperature, Algorithms, Safety, Computer simulation, Design
Proceedings Papers

Performance Analysis for Enhanced Cr-Coated Fuel Cladding System in APR-1400 Reactor

Asma Alzarooni, Mohammad Alrwashdeh, Saeed A. Alameri
Proc. ASME. ICONE31, Volume 11: Student Paper Competition, V011T15A049, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-135127
https://doi.org/10.1115/ICONE31-135127
View Paper titled, Performance Analysis for Enhanced Cr-Coated Fuel Cladding System in APR-1400 Reactor
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Topics: Accidents, Cladding systems (Building), Coating processes, Coatings, Fuels, Pressurized water reactors
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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-91561
https://doi.org/10.1115/ICONE29-91561
View Paper titled, Research on Fretting Wear of Grid and Cladding Tube Under Simulated Primary Circuit Environment of Pressurized Water Reactor
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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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-89017
https://doi.org/10.1115/ICONE29-89017
View Paper titled, Evaluation of the Parameter Importance Changes Over Time for Nuclear Reactor Transients
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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 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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-88944
https://doi.org/10.1115/ICONE29-88944
View Paper titled, A Bi-Layered Three-Dimensional Mechanical Modeling of the Cladding and Its Creep Deformation Analysis
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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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-90521
https://doi.org/10.1115/ICONE29-90521
View Paper titled, Mechanical Performance Assessment of Independently-Developed Zirconium Alloy Under RIA Condition
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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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-93804
https://doi.org/10.1115/ICONE29-93804
View Paper titled, Study of Pre-Oxidization Law and Fretting Wear Resistance of CZ2 Alloy Cladding
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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
Publisher: American Society of Mechanical Engineers
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

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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-90736
https://doi.org/10.1115/ICONE29-90736
View Paper titled, Hydrogenation of Zircaloy-4 in a Defective Fuel Pellet for Pressurized Water Reactors
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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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-93770
https://doi.org/10.1115/ICONE29-93770
View Paper titled, Microstructual and Micro-Chemical Analysis of Zr Cladding Alloys on Corrosion and Creep Properties
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Topics: Alloys, Annealing, Cladding systems (Building), Corrosion, Creep, Tin, Zirconium