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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

Fission Gas Release Grain Boundary Network Percolation Mechanistic Studies in Oxide Fuels Based on COMSOL Multiphysics Framework

Jingyu Guo, Wenzhong Zhou
Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A061, August 8–12, 2022
Paper No: ICONE29-92732
https://doi.org/10.1115/ICONE29-92732
View Paper titled, Fission Gas Release Grain Boundary Network Percolation Mechanistic Studies in Oxide Fuels Based on COMSOL Multiphysics Framework
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Topics: Fuels, Grain boundaries, Nuclear fission, Percolation theory
Proceedings Papers

Multiphysics Analysis of Thorium-Based Fuel Performance Under Reactor Steady-State and Transient Accident

Chenjie Qiu, Rong Liu, Wenzhong Zhou
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, V001T05A010, August 4–5, 2020
Paper No: ICONE2020-16325
https://doi.org/10.1115/ICONE2020-16325
View Paper titled, Multiphysics Analysis of Thorium-Based Fuel Performance Under Reactor Steady-State and Transient Accident
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Topics: Accidents, Fuels, Steady state, Transients (Dynamics)
Proceedings Papers

Numerical Investigation on Pool Boiling Over a Vertical Tube Coupled With In-Tube Condensation

Shuai Ren, Wenzhong Zhou
Proc. ASME. HT2019, ASME 2019 Heat Transfer Summer Conference, V001T10A001, July 14–17, 2019
Paper No: HT2019-3442
https://doi.org/10.1115/HT2019-3442
View Paper titled, Numerical Investigation on Pool Boiling Over a Vertical Tube Coupled With In-Tube Condensation
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Topics: Computational fluid dynamics, Condensation, Pool boiling, Two-phase flow
Proceedings Papers

Multiphysics Modeling of Fabrication Methods’ Effect on UO 2 -BeO Composite Fuels’ Performance

Wei Zhou, Wenzhong Zhou
Proc. ASME. ICONE26, Volume 9: Student Paper Competition, V009T16A026, July 22–26, 2018
Paper No: ICONE26-81429
https://doi.org/10.1115/ICONE26-81429
View Paper titled, Multiphysics Modeling of Fabrication Methods’ Effect on UO 2 -BeO Composite Fuels’ Performance
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Topics: Composite materials, Fuels, Manufacturing, Modeling, Particulate matter, Thermal conductivity, Grain size, Accidents, Microcracks, Nuclear fission
Proceedings Papers

Numerical Simulation of Corium Jet Breakup During Fuel-Coolant Interaction Based on the ALISA Test Performed at KROTOS Test Facility

Pei Shen, Wenzhong Zhou
Proc. ASME. ICONE26, Volume 8: Computational Fluid Dynamics (CFD); Nuclear Education and Public Acceptance, V008T09A028, July 22–26, 2018
Paper No: ICONE26-81818
https://doi.org/10.1115/ICONE26-81818
View Paper titled, Numerical Simulation of Corium Jet Breakup During Fuel-Coolant Interaction Based on the ALISA Test Performed at KROTOS Test Facility
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Topics: Computer simulation, Coolants, Fuels, Test facilities, Explosions, Steam, Accidents, Simulation, China, Computational fluid dynamics
Proceedings Papers

In-Vessel Corium Behavior and Steam Explosion Risks: A Review of Experimental Approaches

Pei Shen, Wenzhong Zhou
Proc. ASME. ICONE25, Volume 7: Fuel Cycle, Decontamination and Decommissioning, Radiation Protection, Shielding, and Waste Management; Mitigation Strategies for Beyond Design Basis Events, V007T11A017, July 2–6, 2017
Paper No: ICONE25-67176
https://doi.org/10.1115/ICONE25-67176
View Paper titled, In-Vessel Corium Behavior and Steam Explosion Risks: A Review of Experimental Approaches
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Topics: Experimental methods, Explosions, Steam, Vessels, Coolants, Heat transfer, Reactor vessels, Accident management, Accidents, Containment
Proceedings Papers

Enhanced Thermal Conductivity UO 2 -GaN Fuel, Proposed Fabrication Methods and Multiphysics Fuel Behavior Analysis

Wei Zhou, Rong Liu, Wenzhong Zhou
Proc. ASME. ICONE25, Volume 9: Student Paper Competition, V009T15A036, July 2–6, 2017
Paper No: ICONE25-67167
https://doi.org/10.1115/ICONE25-67167
View Paper titled, Enhanced Thermal Conductivity UO 2 -GaN Fuel, Proposed Fabrication Methods and Multiphysics Fuel Behavior Analysis
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Topics: Fuels, Gallium nitride, Manufacturing, Thermal conductivity, Composite materials, Nuclear fission, Slug flows, Computer simulation, Displacement, Electrical conductance
Proceedings Papers

Fully Coupled Multiphysics Simulation of Enhanced Thermal Conductivity UO 2 -BeO Fuel Behavior

Rong Liu, Wenzhong Zhou
Proc. ASME. IMECE2015, Volume 6B: Energy, V06BT07A026, November 13–19, 2015
Paper No: IMECE2015-52504
https://doi.org/10.1115/IMECE2015-52504
View Paper titled, Fully Coupled Multiphysics Simulation of Enhanced Thermal Conductivity UO 2 -BeO Fuel Behavior
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Topics: Fuels, Simulation, Thermal conductivity, Cladding systems (Building), Nuclear fission, Light water reactors, Thermal stresses, Cracking (Materials), Creep, Diffusion (Physics)
Journal Articles

Fully Coupled Simulation of Oxygen and Heat Diffusion for ( U , Pu ) O 2 Fuel in Both Fast-Breeder Reactor and Light-Water Reactor

Wenzhong Zhou, Rong Liu
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Research Papers
ASME J of Nuclear Rad Sci. October 2015, 1(4): 041007.
Paper No: NERS-15-1020
https://doi.org/10.1115/1.4031033
Published Online: September 3, 2015
View Article titled, Fully Coupled Simulation of Oxygen and Heat Diffusion for ( U , Pu ) O 2 Fuel in Both Fast-Breeder Reactor and Light-Water Reactor
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Topics: Fuels, Light water reactors, Oxygen, Simulation, Temperature, Fast neutron reactors, Diffusion (Physics), Heat, Boundary-value problems, Thermal diffusion
Proceedings Papers

Fully Coupled Simulation of Oxygen and Heat Diffusion for (U, Pu)O 2 Fuel in Both FBR and LWR

Wenzhong Zhou, Rong Liu
Proc. ASME. IMECE2014, Volume 6B: Energy, V06BT07A031, November 14–20, 2014
Paper No: IMECE2014-40212
https://doi.org/10.1115/IMECE2014-40212
View Paper titled, Fully Coupled Simulation of Oxygen and Heat Diffusion for (U, Pu)O 2 Fuel in Both FBR and LWR
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Topics: Fuels, Light water reactors, Oxygen, Simulation, Thermal diffusion, Metals, Fast neutron reactors, Temperature, Simulation results, Temperature distribution
Proceedings Papers

Three Dimensional Coupled Simulation of Plutonium, Oxygen and Heat Diffusion in Mixed Oxide (U, Pu)O 2 Fast Reactor Fuel

Rong Liu, Wenzhong Zhou, Gang Yang
Proc. ASME. ICONE22, Volume 1: Plant Operations, Maintenance, Engineering, Modifications, Life Cycle and Balance of Plant; Nuclear Fuel and Materials; Plant Systems, Structures and Components; Codes, Standards, Licensing and Regulatory Issues, V001T02A012, July 7–11, 2014
Paper No: ICONE22-30641
https://doi.org/10.1115/ICONE22-30641
View Paper titled, Three Dimensional Coupled Simulation of Plutonium, Oxygen and Heat Diffusion in Mixed Oxide (U, Pu)O 2 Fast Reactor Fuel
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Topics: Fast neutron reactors, Fuels, Oxygen, Simulation, Thermal diffusion, Diffusion (Physics), Density, High temperature, Irradiation (Radiation exposure), Materials properties
Proceedings Papers

Enhanced Thermal Conductivity UO 2 -BeO Fuels Fabrication Methods and Their Thermal Performance in Light Water Reactors

Wenzhong Zhou, Rong Liu
Proc. ASME. ICONE22, Volume 1: Plant Operations, Maintenance, Engineering, Modifications, Life Cycle and Balance of Plant; Nuclear Fuel and Materials; Plant Systems, Structures and Components; Codes, Standards, Licensing and Regulatory Issues, V001T02A013, July 7–11, 2014
Paper No: ICONE22-30647
https://doi.org/10.1115/ICONE22-30647
View Paper titled, Enhanced Thermal Conductivity UO 2 -BeO Fuels Fabrication Methods and Their Thermal Performance in Light Water Reactors
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Topics: Fuels, Light water reactors, Manufacturing, Thermal conductivity, Finite element methods, Nuclear fuels, Composite materials, Computer software, Engineering simulation, Nuclear reactors
Proceedings Papers

Vertical Tube Passive Condenser Under Secondary Pool Water Level Transient

Shripad T. Revankar, Wenzhong Zhou
Proc. ASME. IHTC14, 2010 14th International Heat Transfer Conference, Volume 2, 253-260, August 8–13, 2010
Paper No: IHTC14-23125
https://doi.org/10.1115/IHTC14-23125
View Paper titled, Vertical Tube Passive Condenser Under Secondary Pool Water Level Transient
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Topics: Condensers (steam plant), Transients (Dynamics), Water, Pressure, Steam, Boiling, Condensation, Design, Annulus, Boiling water reactors
Proceedings Papers

Condensation in a Vertical Tube Bundle Operating in Passive Condensation Mode

Gavin Henderson, Wenzhong Zhou, Shripad T. Revankar
Proc. ASME. HT2009, Volume 3: Combustion, Fire and Reacting Flow; Heat Transfer in Multiphase Systems; Heat Transfer in Transport Phenomena in Manufacturing and Materials Processing; Heat and Mass Transfer in Biotechnology; Low Temperature Heat Transfer; Environmental Heat Transfer; Heat Transfer Education; Visualization of Heat Transfer, 435-444, July 19–23, 2009
Paper No: HT2009-88495
https://doi.org/10.1115/HT2009-88495
View Paper titled, Condensation in a Vertical Tube Bundle Operating in Passive Condensation Mode
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Topics: Condensation, Heat transfer, Pressure, Steam, Condensers (steam plant), Containment, Engineering prototypes, Heat transfer coefficients, Cooling systems, Flow (Dynamics)
Proceedings Papers

Experimental Study of Effects of Non-Condensable on Condensation in a Vertical Tube Bundle

Wenzhong Zhou, Gavin Henderson, Shripad T. Revankar
Proc. ASME. HT2009, Volume 3: Combustion, Fire and Reacting Flow; Heat Transfer in Multiphase Systems; Heat Transfer in Transport Phenomena in Manufacturing and Materials Processing; Heat and Mass Transfer in Biotechnology; Low Temperature Heat Transfer; Environmental Heat Transfer; Heat Transfer Education; Visualization of Heat Transfer, 455-464, July 19–23, 2009
Paper No: HT2009-88497
https://doi.org/10.1115/HT2009-88497
View Paper titled, Experimental Study of Effects of Non-Condensable on Condensation in a Vertical Tube Bundle
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Topics: Condensation, Condensers (steam plant), Flow (Dynamics), Steam, Containment, Design, Heat transfer, Pressure, Safety, Accidents
Proceedings Papers

Experimental Study of Non-Condensable Effect on Passive Condenser System

Wenzhong Zhou, Shripad T. Revankar
Proc. ASME. HT2007, ASME/JSME 2007 Thermal Engineering Heat Transfer Summer Conference, Volume 2, 627-634, July 8–12, 2007
Paper No: HT2007-32160
https://doi.org/10.1115/HT2007-32160
View Paper titled, Experimental Study of Non-Condensable Effect on Passive Condenser System
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Topics: Condensers (steam plant), Condensation, Design, Heat, Steam, Boiling, Boiling water reactors, Containment, Cooling systems, Flow (Dynamics)
Proceedings Papers

Scaling of Passive Condenser System Separate Effect Facility

Shripad T. Revankar, Seungmin Oh, Wenzhong Zhou, Gavin Henderson
Proc. ASME. HT2008, Heat Transfer: Volume 2, 219-227, August 10–14, 2008
Paper No: HT2008-56131
https://doi.org/10.1115/HT2008-56131
View Paper titled, Scaling of Passive Condenser System Separate Effect Facility
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Topics: Condensers (steam plant), Engineering prototypes, Test facilities, Containment, Design, Accidents, Boiling water reactors, Condensation, Cooling, Cooling systems