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Proceedings Papers

Study on the Manufacturing Process of Large Super Alloy X-750 Forgings for Nuclear Equipment

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Mei-fang Chen, Sheng-qiang Cao, Kai Dong
Proc. ASME. ICONE29, Volume 10: Advanced Methods of Manufacturing for Nuclear Reactors and Components, V010T10A019, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-91791
https://doi.org/10.1115/ICONE29-91791
View Paper titled, Study on the Manufacturing Process of Large Super Alloy X-750 Forgings for Nuclear Equipment
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Topics: Alloys, Forging, Forgings (Products), Manufacturing, Springs, Temperature, Grain size, Annealing, Creep, Fracture (Materials)
Proceedings Papers

Comparative Study on Creep-Fatigue Damage Assessment Between R5 Procedures and a Full Inelastic Analysis

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Antony M. Hurst, Louis C. W. Chang, Nak-Kyun Cho
Proc. ASME. ICONE29, Volume 12: Innovative and Smart Nuclear Power Plant Design, V012T12A008, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-91707
https://doi.org/10.1115/ICONE29-91707
View Paper titled, Comparative Study on Creep-Fatigue Damage Assessment Between R5 Procedures and a Full Inelastic Analysis
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Topics: Creep, Damage assessment, Fatigue, Inelastic analysis, Stress, Damage, Elastic analysis, Cracking (Materials), Fracture (Process), Geometry
Proceedings Papers

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

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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

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

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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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-93816
https://doi.org/10.1115/ICONE29-93816
View Paper titled, Study on Out-Pile Performance of CZ Zirconium Alloy Guide Tube
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Topics: Corrosion, Creep, Zirconium alloys, Alloys, Zirconium, Corrosion resistance, Stress, Temperature, Mechanical testing, Particulate matter
Proceedings Papers

Creep Properties of FeCrAl Alloy at High Temperature Under Neutron Irradiation

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Huan Yao, Tianzhou Ye, Junmei Wu, Yingwei Wu, Chunyu Yin, Ping Chen
Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A005, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-89079
https://doi.org/10.1115/ICONE29-89079
View Paper titled, Creep Properties of FeCrAl Alloy at High Temperature Under Neutron Irradiation
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Topics: Alloys, Creep, High temperature, Irradiation (Radiation exposure), Neutrons
Proceedings Papers

Creep Performance and Microstructure Evolution of IN617 at 950 °C for VHTR Applications

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Yue Wang, Haitao Wang, Kejian Li
Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A002, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-88939
https://doi.org/10.1115/ICONE29-88939
View Paper titled, Creep Performance and Microstructure Evolution of IN617 at 950 °C for VHTR Applications
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Topics: Creep, Very high temperature reactors
Proceedings Papers

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

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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
Proceedings Papers

Development of an Integrated Design Evaluation ‘HITEP’ Platform for High-Temperature Pressure Boundary Components and Piping Systems

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Hyeong-Yeon Lee, Si-Hwa Jeong, Min-Gu Won, Nam-Su Huh
Proc. ASME. ICONE28, Volume 2: Nuclear Fuels, Research, and Fuel Cycle; Nuclear Codes and Standards; Thermal-Hydraulics, V002T06A004, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-65552
https://doi.org/10.1115/ICONE28-65552
View Paper titled, Development of an Integrated Design Evaluation ‘HITEP’ Platform for High-Temperature Pressure Boundary Components and Piping Systems
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Topics: Creep, Design, High temperature, Pipes, Piping systems, Pressure, Temperature
Proceedings Papers

Stress Analysis of the Pressurized-Water Reactor Control Rod Under Operating Conditions

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Leo A. Carrilho
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, V001T05A015, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16872
https://doi.org/10.1115/ICONE2020-16872
View Paper titled, Stress Analysis of the Pressurized-Water Reactor Control Rod Under Operating Conditions
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Topics: Pressurized water reactors, Stress, Stress analysis (Engineering), Water, Cladding systems (Building), Finite element model, Fluence (Radiation measurement), Temperature, Thermal expansion, Coolants
Proceedings Papers

Numerical Simulation Method Research on Pellet-Cladding Mechanical Interaction Based on ABAQUS Software

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Changbing Tang, Yongjun Jiao, Yuanming Li, Yi Zhou, Kun Zhang
Proc. ASME. ICONE2020, Volume 2: Nuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors, V002T08A036, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16387
https://doi.org/10.1115/ICONE2020-16387
View Paper titled, Numerical Simulation Method Research on Pellet-Cladding Mechanical Interaction Based on ABAQUS Software
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Topics: Cladding systems (Building), Computer simulation, Computer software, Fuel rods, Fuels, Stress, Failure, Pressure, Simulation, Transients (Dynamics)
Proceedings Papers

Improvement of the Evaluation Accuracy for the Diameter Prediction of the CANDU Pressure Tubes

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Jong Yeob Jung
Proc. ASME. ICONE2020, Volume 2: Nuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors, V002T09A007, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16590
https://doi.org/10.1115/ICONE2020-16590
View Paper titled, Improvement of the Evaluation Accuracy for the Diameter Prediction of the CANDU Pressure Tubes
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Topics: Pressure, Creep, Fuels, Irradiation (Radiation exposure), Modeling, Cooling, Deformation, Flow (Dynamics), Heat, Heat transfer
Proceedings Papers

Modelling of the H2020 INSPYRE Fuel Creep Experiment

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Alexander Fedorov, Kevin Zwijsen, Sander van Til
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, V001T05A009, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16231
https://doi.org/10.1115/ICONE2020-16231
View Paper titled, Modelling of the H2020 INSPYRE Fuel Creep Experiment
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Topics: Computer simulation, Creep, Fuels, Modeling, Nuclear fuels
Proceedings Papers

Effect of Final Annealing Temperature on Axial Creep Property of CZ Alloys

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Lin Shi, Liutao Chen, Yang Xu, Changyuan Gao, Jun Tan, Yongjun Deng
Proc. ASME. ICONE26, Volume 3: Nuclear Fuel and Material, Reactor Physics, and Transport Theory, V003T02A025, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81540
https://doi.org/10.1115/ICONE26-81540
View Paper titled, Effect of Final Annealing Temperature on Axial Creep Property of CZ Alloys
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Topics: Alloys, Annealing, Creep, Temperature, Stress, Cladding systems (Building), China, Nuclear power, Pressurized water reactors
Proceedings Papers

First Steps Towards the Development of a 3D Nuclear Fuel Behavior Solver With OpenFOAM

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Alessandro Scolaro, Ivor Clifford, Carlo Fiorina, Andreas Pautz
Proc. ASME. ICONE26, Volume 3: Nuclear Fuel and Material, Reactor Physics, and Transport Theory, V003T02A051, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-82381
https://doi.org/10.1115/ICONE26-82381
View Paper titled, First Steps Towards the Development of a 3D Nuclear Fuel Behavior Solver With OpenFOAM
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Topics: Nuclear fuels, Temperature, Electrical conductance, Fuels, Materials properties, Cracking (Materials), Creep, Databases, Fracture (Process), Fuel rods
Proceedings Papers

Reactor Baffle Cooling CFD Framework for Swelling Assessment

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Yuliia Filonova, Vladislav Filonov, Yaroslav Dubyk
Proc. ASME. ICONE26, Volume 9: Student Paper Competition, V009T16A079, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-82365
https://doi.org/10.1115/ICONE26-82365
View Paper titled, Reactor Baffle Cooling CFD Framework for Swelling Assessment
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Topics: Computational fluid dynamics, Cooling, Temperature distribution, Creep, Geometry, Metals, Boundary-value problems, Convection, Coolants, Deformation
Proceedings Papers

Creep Deformation Analysis of a Pipe Specimen Based on Creep Damage Evaluation Method

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Jinya Katsuyama, Yoshihito Yamaguchi, Yinsheng Li
Proc. ASME. ICONE26, Volume 2: Plant Systems, Structures, Components, and Materials; Risk Assessments and Management, V002T03A032, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-82568
https://doi.org/10.1115/ICONE26-82568
View Paper titled, Creep Deformation Analysis of a Pipe Specimen Based on Creep Damage Evaluation Method
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Topics: Creep, Damage, Evaluation methods, Pipes, Accidents, Constitutive equations, Failure, Failure analysis, Finite element analysis, Fukushima nuclear disaster, Japan, 2011
Proceedings Papers

Probabilistic Analysis of Creep-Induced SGTR for NPP

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Wenjing Li, Wentao Zhu, Xinli Yu, Wei Wei
Proc. ASME. ICONE26, Volume 2: Plant Systems, Structures, Components, and Materials; Risk Assessments and Management, V002T14A001, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81032
https://doi.org/10.1115/ICONE26-81032
View Paper titled, Probabilistic Analysis of Creep-Induced SGTR for NPP
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Topics: Creep, Nuclear power stations, Accidents, Probability, Accident management, Boilers, Failure, Pipes, Pressure, Probabilistic safety assessment
Proceedings Papers

A Structural Integrity Assessment of a Nuclear Boiler Superheater Bifurcation at High Temperature

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Brahim Nadri, Robert X. Wang
Proc. ASME. ICONE26, Volume 2: Plant Systems, Structures, Components, and Materials; Risk Assessments and Management, V002T03A005, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81167
https://doi.org/10.1115/ICONE26-81167
View Paper titled, A Structural Integrity Assessment of a Nuclear Boiler Superheater Bifurcation at High Temperature
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Topics: Bifurcation, Boilers, High temperature, Superheaters, Creep, Metals, Fatigue, Fracture (Materials), Safety, Boiler tubes
Proceedings Papers

A Concept of Intermediate Heat Exchanger for High-Temperature Gas Reactor Hydrogen and Power Cogeneration System

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Noriaki Hirota, Atsuhiko Terada, Xing L. Yan, Kohei Tanaka, Akihito Otani
Proc. ASME. ICONE26, Volume 1: Operations and Maintenance, Engineering, Modifications, Life Extension, Life Cycle, and Balance of Plant; Instrumentation and Control (I&C) and Influence of Human Factors; Innovative Nuclear Power Plant Design and SMRs, V001T13A015, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81718
https://doi.org/10.1115/ICONE26-81718
View Paper titled, A Concept of Intermediate Heat Exchanger for High-Temperature Gas Reactor Hydrogen and Power Cogeneration System
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Topics: Combined heat and power, Heat exchangers, High temperature, Hydrogen, Nuclear reactors, Conceptual design, Design, Gas turbines, Construction, Creep
Proceedings Papers

Structural Integrity Assessment to Justify Increase in Upper Operating Temperature Limit of AGR Dome

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Antony M. Hurst
Proc. ASME. ICONE25, Volume 2: Plant Systems, Structures, Components and Materials, V002T03A067, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-66859
https://doi.org/10.1115/ICONE25-66859
View Paper titled, Structural Integrity Assessment to Justify Increase in Upper Operating Temperature Limit of AGR Dome
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Topics: Domes (Structural elements), Operating temperature, Temperature, Failure, Creep, Safety, Welded joints, Diaphragms (Mechanical devices), Diaphragms (Structural), Failure mechanisms