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Proceedings Papers

Simulation on the Multidimensional Behavior of TRISO Particle Fuel With UN/ UO 2 Kernel

Changwei Wu, Junmei Wu, Yanan He, Yingwei Wu
Proc. ASME. ICONE29, Volume 15: Student Paper Competition, V015T16A020, August 8–12, 2022
Paper No: ICONE29-90307
https://doi.org/10.1115/ICONE29-90307
View Paper titled, Simulation on the Multidimensional Behavior of TRISO Particle Fuel With UN/ UO 2 Kernel
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Topics: Fuels, Particulate matter, Simulation, Thermomechanics
Proceedings Papers

Integral Simulation on the Thermo-Mechanical Behavior of the UMo/Al Dispersion Fuel Plate Using Finite Element Method

Guangliang Yang, Wenpei Feng, Tao Ding, Hongli Chen
Proc. ASME. ICONE29, Volume 15: Student Paper Competition, V015T16A028, August 8–12, 2022
Paper No: ICONE29-90559
https://doi.org/10.1115/ICONE29-90559
View Paper titled, Integral Simulation on the Thermo-Mechanical Behavior of the UMo/Al Dispersion Fuel Plate Using Finite Element Method
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Topics: Finite element methods, Fuels, Simulation, Thermomechanics
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
https://doi.org/10.1115/ICONE29-92285
View Paper titled, Investigation of Swelling Behaviors of U-10Zr Metallic Fuel in the Low Temperature Regime via a Combined Thermo-Mechanical and Rate Theory Analysis
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Topics: Fuels, Low temperature, Thermomechanics, Uranium, Zirconium
Proceedings Papers

Multiphysics Thermo-Mechanical Behavior Modeling for Annular Uranium-Plutonium Mixed Oxide Fuels in a Lead-Cooled Fast Reactor

Yutai Cai, Wenzhong Zhou, Long Gu
Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A041, August 8–12, 2022
Paper No: ICONE29-91817
https://doi.org/10.1115/ICONE29-91817
View Paper titled, Multiphysics Thermo-Mechanical Behavior Modeling for Annular Uranium-Plutonium Mixed Oxide Fuels in a Lead-Cooled Fast Reactor
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Topics: Fast neutron reactors, Fuels, Modeling, Thermomechanics, Uranium
Proceedings Papers

Modeling of Irradiation-Induced Thermo-Mechanical Coupling Behavior in Metal Matrix Microencapsulated Fuel

Hongyang Wei, Fawen Zhu, Jun Ru, Haoyu Wang, Jing Zhang, Hua Li, Yun Li, Chunlan Huang, Yuanming Li, Shurong Ding
Proc. ASME. ICONE28, Volume 2: Nuclear Fuels, Research, and Fuel Cycle; Nuclear Codes and Standards; Thermal-Hydraulics, V002T05A016, August 4–6, 2021
Paper No: ICONE28-65563
https://doi.org/10.1115/ICONE28-65563
View Paper titled, Modeling of Irradiation-Induced Thermo-Mechanical Coupling Behavior in Metal Matrix Microencapsulated Fuel
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Topics: Finite element analysis, Fuels, Irradiation (Radiation exposure), Metals, Modeling, Thermomechanics
Proceedings Papers

The Effect of Flow Channel Geometry on Thermomechanical Performance of Printed Circuit Heat Exchanger (PCHE)

Witiwat Jiragoontansiri, Teerapat Woravisuttsarakul, Rinrada Sae-pueng, Yanin Sukjai, Koroush Shirvan
Proc. ASME. ICONE28, Volume 4: Student Paper Competition, V004T14A075, August 4–6, 2021
Paper No: ICONE28-65609
https://doi.org/10.1115/ICONE28-65609
View Paper titled, The Effect of Flow Channel Geometry on Thermomechanical Performance of Printed Circuit Heat Exchanger (PCHE)
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Topics: Circuits, Computational fluid dynamics, Flow (Dynamics), Geometry, Heat exchangers, Structural analysis, Thermomechanics
Proceedings Papers

Thermo-Mechanical Analysis of Instrumentation Guide Tube Failure During a Severe Accident in a Nordic Boiling Water Reactor

Ying Yue, Walter Villanueva, Hongdi Wang, Dingqu Wang
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, V001T01A003, August 4–5, 2020
Paper No: ICONE2020-16236
https://doi.org/10.1115/ICONE2020-16236
View Paper titled, Thermo-Mechanical Analysis of Instrumentation Guide Tube Failure During a Severe Accident in a Nordic Boiling Water Reactor
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Topics: Accidents, Boiling water reactors, Failure, Failure mechanisms, Instrumentation, Thermomechanics
Proceedings Papers

A Revised Methodology to Assess In-Vessel Retention Strategy for High-Power Reactors

F. Fichot, L. Carénini, W. Villanueva, S. Bechta
Proc. ASME. ICONE26, Volume 7: Decontamination and Decommissioning, Radiation Protection, and Waste Management; Mitigation Strategies for Beyond Design Basis Events, V007T11A014, July 22–26, 2018
Paper No: ICONE26-82248
https://doi.org/10.1115/ICONE26-82248
View Paper titled, A Revised Methodology to Assess In-Vessel Retention Strategy for High-Power Reactors
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Topics: Vessels, Safety, Transients (Dynamics), Flux (Metallurgy), Heat, Metals, Light water reactors, Critical heat flux, Heat flux, Steady state
Proceedings Papers

Assessment of Failure Modes of Monolithic Fuel Plates

Hakan Ozaltun, Pavel G. Medvedev, Barry H. Rabin
Proc. ASME. ICONE26, Volume 3: Nuclear Fuel and Material, Reactor Physics, and Transport Theory, V003T02A055, July 22–26, 2018
Paper No: ICONE26-82437
https://doi.org/10.1115/ICONE26-82437
View Paper titled, Assessment of Failure Modes of Monolithic Fuel Plates
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Topics: Failure mechanisms, Fuels, Plates (structures), Failure, Irradiation (Radiation exposure), Tension, Fuel systems, Porosity, Simulation results, Thermomechanics
Proceedings Papers

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

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
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

Investigation on DDC Susceptibility of 690 Nickel-Alloy Welding Wire

Yu Gu, Bo Zuo, Junbao Zhang, Yifeng Huang, Yan Yu
Proc. ASME. ICONE25, Volume 2: Plant Systems, Structures, Components and Materials, V002T03A027, July 2–6, 2017
Paper No: ICONE25-66271
https://doi.org/10.1115/ICONE25-66271
View Paper titled, Investigation on DDC Susceptibility of 690 Nickel-Alloy Welding Wire
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Topics: Nickel alloys, Welding, Wire, Metals, Fracture (Process), Nickel, Alloys, Cladding systems (Building), Ductility, Electron backscatter diffraction
Proceedings Papers

Effect of Fuel Meat Thickness on the Non-Uniform Irradiation-Induced Thermo-Mechanical Behavior in Monolithic UMo/Al Fuel Plates

Feng Yan, Yunmei Zhao, Shurong Ding
Proc. ASME. ICONE25, Volume 3: Nuclear Fuel and Material, Reactor Physics and Transport Theory; Innovative Nuclear Power Plant Design and New Technology Application, V003T02A057, July 2–6, 2017
Paper No: ICONE25-67531
https://doi.org/10.1115/ICONE25-67531
View Paper titled, Effect of Fuel Meat Thickness on the Non-Uniform Irradiation-Induced Thermo-Mechanical Behavior in Monolithic UMo/Al Fuel Plates
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Topics: Fuels, Irradiation (Radiation exposure), Plates (structures), Thermomechanics, Stress, Algorithms, Constitutive equations, Deformation, Density, Design
Proceedings Papers

Three Dimensional Modeling of the Thermo-Mechanical Performance of the Fuel Rods of a PWR

Wang Zhu, Zhang Chunyu, Li Aolin, Yuan Cenxi
Proc. ASME. ICONE25, Volume 3: Nuclear Fuel and Material, Reactor Physics and Transport Theory; Innovative Nuclear Power Plant Design and New Technology Application, V003T02A001, July 2–6, 2017
Paper No: ICONE25-66010
https://doi.org/10.1115/ICONE25-66010
View Paper titled, Three Dimensional Modeling of the Thermo-Mechanical Performance of the Fuel Rods of a PWR
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Topics: Fuel rods, Pressurized water reactors, Thermomechanics, Three-dimensional modeling, Stress, Temperature, Accidents, Cladding systems (Building), Displacement, Finite element analysis
Proceedings Papers

Load Following by Cogeneration: Options for Small Modular Reactors, GEN IV Reactor and Traditional Large Plants

Giorgio Locatelli, Andrea Fiordaliso, Sara Boarin, Marco Ricotti
Proc. ASME. ICONE25, Volume 3: Nuclear Fuel and Material, Reactor Physics and Transport Theory; Innovative Nuclear Power Plant Design and New Technology Application, V003T13A013, July 2–6, 2017
Paper No: ICONE25-67180
https://doi.org/10.1115/ICONE25-67180
View Paper titled, Load Following by Cogeneration: Options for Small Modular Reactors, GEN IV Reactor and Traditional Large Plants
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Topics: Combined heat and power, Small modular reactors, Stress, Nuclear power stations, Electricity (Physics), Water, Circuits, Diesel, Fuels, Hydrogen
Proceedings Papers

Fundamental R&D Work on Methods for State Monitoring of Transport and Storage Containers for Spent Fuel and Heat-Generating High-Level Radioactive Waste on Prolonged Intermediate Storage

Daniel Fiß, Sebastian Schmidt, Sebastian Reinicke, Alexander Kratzsch
Proc. ASME. ICONE25, Volume 9: Student Paper Competition, V009T15A039, July 2–6, 2017
Paper No: ICONE25-67245
https://doi.org/10.1115/ICONE25-67245
View Paper titled, Fundamental R&D Work on Methods for State Monitoring of Transport and Storage Containers for Spent Fuel and Heat-Generating High-Level Radioactive Waste on Prolonged Intermediate Storage
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Topics: Containers, Heat, Radioactive wastes, Spent nuclear fuels, Storage, Acoustics, Condition monitoring, Emissions, Fuel rods, Modeling
Proceedings Papers

Probabilistic Prediction of Fatigue Life of Pipes Under Turbulent Fluid Mixing

Oriol Costa Garrido, Leon Cizelj
Proc. ASME. ICONE24, Volume 5: Student Paper Competition, V005T15A010, June 26–30, 2016
Paper No: ICONE24-60194
https://doi.org/10.1115/ICONE24-60194
View Paper titled, Probabilistic Prediction of Fatigue Life of Pipes Under Turbulent Fluid Mixing
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Topics: Fatigue life, Fluids, Pipes, Turbulence, Temperature, Uncertainty, Fatigue, Transients (Dynamics), Flow (Dynamics), Fluctuations (Physics)
Proceedings Papers

Effect of Cooling Rates on Mechanical Behavior of U-10Mo Monolithic Mini-Plate

Hee Seok Roh, Walid Mohamed
Proc. ASME. ICONE24, Volume 1: Operations and Maintenance, Aging Management and Plant Upgrades; Nuclear Fuel, Fuel Cycle, Reactor Physics and Transport Theory; Plant Systems, Structures, Components and Materials; I&C, Digital Controls, and Influence of Human Factors, V001T02A026, June 26–30, 2016
Paper No: ICONE24-60747
https://doi.org/10.1115/ICONE24-60747
View Paper titled, Effect of Cooling Rates on Mechanical Behavior of U-10Mo Monolithic Mini-Plate
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Topics: Cooling, Mechanical behavior, Coolants, Stress, Heat transfer coefficients, Cladding systems (Building), Finite element analysis, Flow (Dynamics), Fuels, Numerical analysis
Proceedings Papers

Effects of Cladding Material on Irradiation Performance of Monolithic Mini-Plates

Hakan Ozaltun
Proc. ASME. ICONE24, Volume 1: Operations and Maintenance, Aging Management and Plant Upgrades; Nuclear Fuel, Fuel Cycle, Reactor Physics and Transport Theory; Plant Systems, Structures, Components and Materials; I&C, Digital Controls, and Influence of Human Factors, V001T02A009, June 26–30, 2016
Paper No: ICONE24-60120
https://doi.org/10.1115/ICONE24-60120
View Paper titled, Effects of Cladding Material on Irradiation Performance of Monolithic Mini-Plates
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Topics: Cladding systems (Building), Irradiation (Radiation exposure), Plates (structures), Fuels, Stress, Aluminum, Alloys, Density, Diffusion (Physics), Displacement
Proceedings Papers

Experimental Activity for the Investigation of Mixing and Thermal Stratification Phenomena in the CIRCE Pool Facility

D. Martelli, M. Tarantino, I. Di Piazza
Proc. ASME. ICONE24, Volume 4: Computational Fluid Dynamics (CFD) and Coupled Codes; Decontamination and Decommissioning, Radiation Protection, Shielding, and Waste Management; Workforce Development, Nuclear Education and Public Acceptance; Mitigation Strategies for Beyond Design Basis Events; Risk Management, V004T10A027, June 26–30, 2016
Paper No: ICONE24-60920
https://doi.org/10.1115/ICONE24-60920
View Paper titled, Experimental Activity for the Investigation of Mixing and Thermal Stratification Phenomena in the CIRCE Pool Facility
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Topics: Thermal stratification, Fuels, Fast neutron reactors, Safety, Design, Flow (Dynamics), Heat, Heat sinks, Heat transfer, Liquid metals
Proceedings Papers

Effects of the Foil Centering on the Irradiation Performance of U10Mo Alloy Based Monolithic Mini-Plates

Jill Wright, Hakan Ozaltun
Proc. ASME. NUCLRF2015, ASME 2015 Nuclear Forum, V001T03A003, June 28–July 2, 2015
Paper No: NUCLRF2015-49462
https://doi.org/10.1115/NUCLRF2015-49462
View Paper titled, Effects of the Foil Centering on the Irradiation Performance of U10Mo Alloy Based Monolithic Mini-Plates
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Topics: Alloys, Irradiation (Radiation exposure), Plates (structures), Fuels, Cladding systems (Building), Cooling, Engineering simulation, Manufacturing, Simulation, Warping