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Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A005, August 8–12, 2022

Paper No: ICONE29-89079

DOI: https://doi.org/10.1115/ICONE29-89079

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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

Paper No: ICONE2020-16291

DOI: https://doi.org/10.1115/ICONE2020-16291

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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

ASME J of Nuclear Rad Sci. October 2019, 5(4): 041302.

Paper No: NERS-18-1073

DOI: https://doi.org/10.1115/1.4042364

Published Online: July 19, 2019

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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

ASME J of Nuclear Rad Sci. January 2019, 5(1): 011015.

Paper No: NERS-17-1293

DOI: https://doi.org/10.1115/1.4041194

Published Online: January 24, 2019

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Topics: Accidents, Cladding systems (Building), Fuels, Stress, Pressure, Simulation, Coatings, Zirconium

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

Paper No: ICONE26-81505

DOI: https://doi.org/10.1115/ICONE26-81505

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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

Paper No: ICONE26-82076

DOI: https://doi.org/10.1115/ICONE26-82076

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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

Paper No: ICONE26-81248

DOI: https://doi.org/10.1115/ICONE26-81248

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Topics: China, Sodium fast reactors, Flow (Dynamics), Pumps, Reliability, Safety, Accidents, Coolants, Design, Engineering prototypes

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

Paper No: ICONE26-81891

DOI: https://doi.org/10.1115/ICONE26-81891

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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

Paper No: ICONE26-81444

DOI: https://doi.org/10.1115/ICONE26-81444

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Topics: Pressure drop, Sodium, Heat flux, Pressure, Temperature

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

ASME J of Nuclear Rad Sci. October 2018, 4(4): 041002.

Paper No: NERS-17-1163

DOI: https://doi.org/10.1115/1.4040887

Published Online: September 10, 2018

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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

Paper No: ICONE25-66009

DOI: https://doi.org/10.1115/ICONE25-66009

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Topics: Liquid metals, Safety, Sodium fast reactors, Fluids, Sodium, Temperature, Vapors, Water, Boilers, Boiling

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

Paper No: ICONE25-66774

DOI: https://doi.org/10.1115/ICONE25-66774

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Topics: Accidents, Cladding systems (Building), Fuels, Simulation, Coatings, Zirconium, Alloys, Fuel rods, Pressure, Stress

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

Paper No: ICONE25-66523

DOI: https://doi.org/10.1115/ICONE25-66523

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Topics: Accidents, Cladding systems (Building), Oxidation, Sensitivity analysis, Simulation, Fuels, Alloys, Design, Fukushima nuclear disaster, Japan, 2011, Hydrogen

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

Paper No: ICONE24-60583

DOI: https://doi.org/10.1115/ICONE24-60583

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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

Paper No: ICONE24-60392

DOI: https://doi.org/10.1115/ICONE24-60392

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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

Paper No: ICONE24-60432

DOI: https://doi.org/10.1115/ICONE24-60432

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Topics: China, Containment, Cooling, Design, Domes (Structural elements), Errors, Flow (Dynamics), Heat, Helium, Nuclear engineering

Proceedings Papers

A Prediction of the Leakage Through Cracks for Leak Before Break

Jing Zhang, Yingwei Wu, Lei Ding, Hongwei Qiao, Pengzhou Li, Guanghui Su, Suizheng Qiu, Wenxi Tian

Proc. ASME. ICONE22, Volume 2B: Thermal Hydraulics, V02BT09A018, July 7–11, 2014

Paper No: ICONE22-30708

DOI: https://doi.org/10.1115/ICONE22-30708

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Topics: Fracture (Materials), Leakage, Leak-before-break, Flow (Dynamics), Surface roughness, Corners (Structural elements), Displacement, Enthalpy, Fluids, Friction

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

Paper No: ICONE22-30881

DOI: https://doi.org/10.1115/ICONE22-30881

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Topics: Combustion, Economics , Fast neutron reactors, Radioactive wastes, Safety, Water

Journal citation

NARROW

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

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

Creep Properties of FeCrAl Alloy at High Temperature Under Neutron Irradiation

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

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

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

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

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

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

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

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

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

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

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

Accident Tolerance Cladding Thermal Hydraulic Simulation and Oxidation Kinetic Sensitivity Analysis

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

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

Validation of the ATHROC Code With NUPEC Tests

A Prediction of the Leakage Through Cracks for Leak Before Break

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

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