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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
Publisher: American Society of Mechanical Engineers
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

Preliminary Development of a Coupling Environment Based on MOOSE and OpenFOAM and Its Application on Plate Fuel Modeling

Hongquan Liu, Yanan He, Yingwei Wu, Guanghui Su, Wenxi Tian, Suizheng Qiu
Proc. ASME. ICONE29, Volume 15: Student Paper Competition, V015T16A044, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-91437
https://doi.org/10.1115/ICONE29-91437
View Paper titled, Preliminary Development of a Coupling Environment Based on MOOSE and OpenFOAM and Its Application on Plate Fuel Modeling
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Topics: Fuels, Heat transfer, Modeling, Physics, Process control, Computational fluid dynamics, Nuclear reactors, Simulation, Convection, Finite element analysis
Proceedings Papers

Creep Properties of FeCrAl Alloy at High Temperature Under Neutron Irradiation

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

Modeling Axial Relocation of Fragmented Fuel During Loss of Coolant Conditions by Using ABAQUS

Zehua Ma, Koroush Shirvan, Wei Li, Yingwei Wu
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, V001T01A006, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16291
https://doi.org/10.1115/ICONE2020-16291
View Paper titled, Modeling Axial Relocation of Fragmented Fuel During Loss of Coolant Conditions by Using ABAQUS
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Topics: Accidents, Coolants, Fuels, Modeling
Journal Articles

Neutronic and Thermo-Hydraulic Analyses of Water-Cooled Blanket Based on Pressurized/Supercritical Water Conditions for CFETR

Jie Cheng, Yingwei Wu, G. H. Su, Suizheng Qiu, Wenxi Tian
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2019, 5(4): 041302.
Paper No: NERS-18-1073
https://doi.org/10.1115/1.4042364
Published Online: July 19, 2019
View Article titled, Neutronic and Thermo-Hydraulic Analyses of Water-Cooled Blanket Based on Pressurized/Supercritical Water Conditions for CFETR
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Topics: Water, Flow (Dynamics), Design, Simulation
Journal Articles

Simulation on Pellet–Cladding Mechanical Interaction of Accident Tolerant Fuel With Coated Cladding

Yangbin Deng, Yingwei Wu, Dalin Zhang, Wenxi Tian, G. H. Su, Suizheng Qiu
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2019, 5(1): 011015.
Paper No: NERS-17-1293
https://doi.org/10.1115/1.4041194
Published Online: January 24, 2019
View Article titled, Simulation on Pellet–Cladding Mechanical Interaction of Accident Tolerant Fuel With Coated Cladding
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Topics: Accidents, Cladding systems (Building), Fuels, Stress, Pressure, Simulation, Coatings, Zirconium
Proceedings Papers

Numerical and Experimental Investigation on Core Assembly Thermal-Gradient-Induced Deformation of Sodium-Cooled Fast Reactor

Zehua Ma, Yingwei Wu, G. H. Su, Wenxi Tian, Suizheng Qiu
Proc. ASME. ICONE26, Volume 9: Student Paper Competition, V009T16A063, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81891
https://doi.org/10.1115/ICONE26-81891
View Paper titled, Numerical and Experimental Investigation on Core Assembly Thermal-Gradient-Induced Deformation of Sodium-Cooled Fast Reactor
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Topics: Deformation, Manufacturing, Sodium fast reactors, Temperature gradient, Computation, Displacement, Finite element model, Friction, Reliability, Rods
Proceedings Papers

Pressure Drop Experiments of Liquid Sodium Flowing in a 7-Rod Bundle

Yandong Hou, Liu Wang, Yingwei Wu, Wenxi Tian, Suizheng Qiu, G. H. Su
Proc. ASME. ICONE26, Volume 9: Student Paper Competition, V009T16A028, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81444
https://doi.org/10.1115/ICONE26-81444
View Paper titled, Pressure Drop Experiments of Liquid Sodium Flowing in a 7-Rod Bundle
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Topics: Pressure drop, Sodium, Heat flux, Pressure, Temperature
Proceedings Papers

Experimental Study on Spray Pattern of Pressure-Swirl Nozzle in Reactor Containment

Jiawei Bian, Dalin Zhang, Rulei Sun, Yingwei Wu, Wenxi Tian, G. H. Su, Suizheng Qiu
Proc. ASME. ICONE26, Volume 9: Student Paper Competition, V009T16A033, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81505
https://doi.org/10.1115/ICONE26-81505
View Paper titled, Experimental Study on Spray Pattern of Pressure-Swirl Nozzle in Reactor Containment
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Topics: Containment, Nozzles, Pressure, Sprays, Plasma spraying, Spraying (Coating processes), Design, Drops, Optimization, Pressurized water reactors
Proceedings Papers

Analysis of UO 2 -BeO Fuel Performance During Normal Conditions and RIA

Yanan He, Yingwei Wu, Shihuai Wang, Bowen Qiu, G. H. Su
Proc. ASME. ICONE26, Volume 9: Student Paper Competition, V009T16A070, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-82076
https://doi.org/10.1115/ICONE26-82076
View Paper titled, Analysis of UO 2 -BeO Fuel Performance During Normal Conditions and RIA
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Topics: Fuels, Composite materials, Light water reactors, Accidents, Nuclear fission, Thermal conductivity, Thermal properties, Cladding systems (Building), Coolants, Enthalpy
Proceedings Papers

Characterization and Experimental Investigation for the Dynamic Performance of the Hydraulically Suspended Passive Shutdown System in China Sodium-Cooled Fast Reactor

Jian Song, Yingwei Wu, Wenxi Tian, Suizheng Qiu, Guanghui Su
Proc. ASME. ICONE26, Volume 9: Student Paper Competition, V009T16A016, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81248
https://doi.org/10.1115/ICONE26-81248
View Paper titled, Characterization and Experimental Investigation for the Dynamic Performance of the Hydraulically Suspended Passive Shutdown System in China Sodium-Cooled Fast Reactor
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Topics: China, Sodium fast reactors, Flow (Dynamics), Pumps, Reliability, Safety, Accidents, Coolants, Design, Engineering prototypes
Journal Articles

Iron–Chromium–Aluminum (FeCrAl) Cladding Oxidation Kinetics and Auxiliary Feedwater Sensitivity Analysis—Short-Term Station Blackout Simulation of Surry Nuclear Power Plant

Jun Wang, Mckinleigh Mccabe, Troy Christopher Haskin, Yingwei Wu, Guanghui Su, Michael L. Corradini
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2018, 4(4): 041002.
Paper No: NERS-17-1163
https://doi.org/10.1115/1.4040887
Published Online: September 10, 2018
View Article titled, Iron–Chromium–Aluminum (FeCrAl) Cladding Oxidation Kinetics and Auxiliary Feedwater Sensitivity Analysis—Short-Term Station Blackout Simulation of Surry Nuclear Power Plant
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Topics: Cladding systems (Building), Oxidation, Sensitivity analysis, Boilers, Simulation, Feedwater, Water, Temperature, Underground injection, Nuclear power stations
Proceedings Papers

Implementation of Liquid Metal Properties in RELAP5 MOD3.2 for Safety Analysis of Sodium-Cooled Fast Reactors

Jian Song, Limin Liu, Simiao Tang, Yingwei Wu, Wenxi Tian, Suizheng Qiu, Guanghui Su
Proc. ASME. ICONE25, Volume 9: Student Paper Competition, V009T15A002, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-66009
https://doi.org/10.1115/ICONE25-66009
View Paper titled, Implementation of Liquid Metal Properties in RELAP5 MOD3.2 for Safety Analysis of Sodium-Cooled Fast Reactors
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Topics: Liquid metals, Safety, Sodium fast reactors, Fluids, Sodium, Temperature, Vapors, Water, Boilers, Boiling
Proceedings Papers

Accident Tolerance Cladding Thermal Hydraulic Simulation and Oxidation Kinetic Sensitivity Analysis

Jun Wang, Mckinleigh Mccabe, Troy Christopher Haskin, Yingwei Wu, Guanghui Su, Michael L. Corradini
Proc. ASME. ICONE25, Volume 6: Thermal-Hydraulics, V006T08A036, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-66523
https://doi.org/10.1115/ICONE25-66523
View Paper titled, Accident Tolerance Cladding Thermal Hydraulic Simulation and Oxidation Kinetic Sensitivity Analysis
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Topics: Accidents, Cladding systems (Building), Oxidation, Sensitivity analysis, Simulation, Fuels, Alloys, Design, Fukushima nuclear disaster, Japan, 2011, Hydrogen
Proceedings Papers

Simulation on Pellet-Cladding Mechanical Interaction (PCMI) of Accident Tolerant Fuel (ATF) With Coated Cladding

Yangbin Deng, Bowen Qiu, Yingwei Wu, Dalin Zhang, Wenxi Tian, Suizheng Qiu, G. H. Su
Proc. ASME. ICONE25, Volume 3: Nuclear Fuel and Material, Reactor Physics and Transport Theory; Innovative Nuclear Power Plant Design and New Technology Application, V003T02A027, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-66774
https://doi.org/10.1115/ICONE25-66774
View Paper titled, Simulation on Pellet-Cladding Mechanical Interaction (PCMI) of Accident Tolerant Fuel (ATF) With Coated Cladding
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Topics: Accidents, Cladding systems (Building), Fuels, Simulation, Coatings, Zirconium, Alloys, Fuel rods, Pressure, Stress
Proceedings Papers

Mechanism Study and Numerical Simulation on Blistering of Plate-Type Fuel

Yangbin Deng, Dalin Zhang, Qing Lu, Yingwei Wu, Wenxi Tian, Suizheng Qiu, G. H. Su
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, V001T02A022, June 26–30, 2016
Publisher: American Society of Mechanical Engineers
Paper No: ICONE24-60583
https://doi.org/10.1115/ICONE24-60583
View Paper titled, Mechanism Study and Numerical Simulation on Blistering of Plate-Type Fuel
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Topics: Computer simulation, Fuels, Cladding systems (Building), Plates (structures), Power density, Computational fluid dynamics, Damage, Deformation, Delays, Fuel rods
Proceedings Papers

Neutronics and Thermo-Hydraulic Analysis of Water-Cooled Blanket Based on PWR and SCWR Water Conditions for CFETR

Jie Cheng, Yingwei Wu, G. H. Su, Suizheng Qiu, Wenxi Tian
Proc. ASME. ICONE24, Volume 2: Smart Grids, Grid Stability, and Offsite and Emergency Power; Advanced and Next Generation Reactors, Fusion Technology; Safety, Security, and Cyber Security; Codes, Standards, Conformity Assessment, Licensing, and Regulatory Issues, V002T06A017, June 26–30, 2016
Publisher: American Society of Mechanical Engineers
Paper No: ICONE24-60392
https://doi.org/10.1115/ICONE24-60392
View Paper titled, Neutronics and Thermo-Hydraulic Analysis of Water-Cooled Blanket Based on PWR and SCWR Water Conditions for CFETR
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Topics: Pressurized water reactors, Supercritical water reactors, Water, China, Heat, Temperature, Bridges (Structures), Ceramics, Computer simulation, Coolants
Proceedings Papers

Validation of the ATHROC Code With NUPEC Tests

Yongzheng Chen, Yingwei Wu, Wenxi Tian, Suizheng Qiu, Guanghui Su
Proc. ASME. ICONE24, Volume 5: Student Paper Competition, V005T15A025, June 26–30, 2016
Publisher: American Society of Mechanical Engineers
Paper No: ICONE24-60432
https://doi.org/10.1115/ICONE24-60432
View Paper titled, Validation of the ATHROC Code With NUPEC Tests
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Topics: China, Containment, Cooling, Design, Domes (Structural elements), Errors, Flow (Dynamics), Heat, Helium, Nuclear engineering
Proceedings Papers

Experimental Study on the Thermal Hydraulic Characteristics of Liquid Sodium Flowing in an Annulus

Zicheng Qiu, Zaiyong Ma, Suizheng Qiu, Yingwei Wu, Guanghui Su
Proc. ASME. ICONE22, Volume 2A: Thermal Hydraulics, V02AT09A025, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-30244
https://doi.org/10.1115/ICONE22-30244
View Paper titled, Experimental Study on the Thermal Hydraulic Characteristics of Liquid Sodium Flowing in an Annulus
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Topics: Annulus, Sodium, Flow (Dynamics), Fluids, Heat flux, Temperature, Friction, Heat transfer coefficients, Laminar flow, Turbulence
Proceedings Papers

Sub-Channel Analysis of Pb-Bi-Cooled Reactor With Modified COBRA-EN

Yonghong Tian, Wenxi Tian, Zhaoming Meng, Yingwei Wu, Guanghui Su, Suizheng Qiu
Proc. ASME. ICONE22, Volume 2B: Thermal Hydraulics, V02BT09A028, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-30881
https://doi.org/10.1115/ICONE22-30881
View Paper titled, Sub-Channel Analysis of Pb-Bi-Cooled Reactor With Modified COBRA-EN
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Topics: Combustion, Economics , Fast neutron reactors, Radioactive wastes, Safety, Water