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Proceedings Papers

Numerical Analysis on the Thermal-Hydraulic Characteristics for the Reactor Main Vessel Cooling System of Chinese Sodium Cooled Fast Reactor

Ping Song, Tangtao Feng, Dalin Zhang, Lie Chen, Shaodan Li, Yuansheng Lin, Suizheng Qiu
Proc. ASME. ICONE28, Volume 2: Nuclear Fuels, Research, and Fuel Cycle; Nuclear Codes and Standards; Thermal-Hydraulics, V002T07A012, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-64293
https://doi.org/10.1115/ICONE28-64293
View Paper titled, Numerical Analysis on the Thermal-Hydraulic Characteristics for the Reactor Main Vessel Cooling System of Chinese Sodium Cooled Fast Reactor
Open the PDF for Numerical Analysis on the Thermal-Hydraulic Characteristics for the Reactor Main Vessel Cooling System of Chinese Sodium Cooled Fast Reactor in another window
Topics: Cooling systems, Numerical analysis, Reactor vessels, Sodium fast reactors, Vessels
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

CFD Investigation of Thermal-Hydraulic Behaviors in Full Reactor Core for Sodium-Cooled Fast Reactor

Jing Chen, Dalin Zhang, Suizheng Qiu, Kui Zhang, Mingjun Wang, G. H. Su
Proc. ASME. ICONE26, Volume 9: Student Paper Competition, V009T16A040, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81626
https://doi.org/10.1115/ICONE26-81626
View Paper titled, CFD Investigation of Thermal-Hydraulic Behaviors in Full Reactor Core for Sodium-Cooled Fast Reactor
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Topics: Computational fluid dynamics, Sodium fast reactors, Flow (Dynamics), China, Computer software, Coolants, Design, Fast neutron reactors, Fluids, Heat
Proceedings Papers

Study on Thermal-Hydraulic Characteristics of Vertical Narrow Rectangular Channel With Large Aspect Ratio Under Transverse Uneven Heating

Rulei Sun, Yichen Yang, Dalin Zhang, Jiawei Bian, Suizheng Qiu, G. H. Su
Proc. ASME. ICONE26, Volume 9: Student Paper Competition, V009T16A050, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81757
https://doi.org/10.1115/ICONE26-81757
View Paper titled, Study on Thermal-Hydraulic Characteristics of Vertical Narrow Rectangular Channel With Large Aspect Ratio Under Transverse Uneven Heating
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Topics: Heating, Fuels, Heat transfer, Flow (Dynamics), Temperature, Coolants, Design, Fluids, Plates (structures), Radiation (Physics)
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

The Choose of Decay Heat Removal Systems of SFR

Nina Yue, Rong Cai, Yun Wang, Suizheng Qiu, Dalin Zhang
Proc. ASME. ICONE26, Volume 6A: Thermal-Hydraulics and Safety Analyses, V06AT08A053, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81563
https://doi.org/10.1115/ICONE26-81563
View Paper titled, The Choose of Decay Heat Removal Systems of SFR
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Topics: Heat, Sodium fast reactors, Cooling systems, Accidents, Flow (Dynamics), Heat exchangers, Nuclear reactors, Safety, Sodium, Systems analysis
Proceedings Papers

Development and Basic Verification of Decay Heat Removal Analysis Code of Sodium-Cooled Fast Reactor

Ping Song, Dalin Zhang, Tangtao Feng, Shibao Wang, Yapei Zhang, Mingjun Wang, Suizheng Qiu, G. H. Su
Proc. ASME. ICONE26, Volume 6A: Thermal-Hydraulics and Safety Analyses, V06AT08A061, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81630
https://doi.org/10.1115/ICONE26-81630
View Paper titled, Development and Basic Verification of Decay Heat Removal Analysis Code of Sodium-Cooled Fast Reactor
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Topics: Heat, Sodium fast reactors, Accidents, Design, China, Circuits, Errors, Fast neutron reactors, Flow (Dynamics), Generation IV reactors
Proceedings Papers

Validation of a Code and Effect of Turbulence Model on Predicting Thermal Stratification Phenomena in the Upper Plenum of SFR

Shibao Wang, Dalin Zhang, Chenglong Wang, Ping Song, Jing Chen, Suizheng Qiu, Guanghui Su
Proc. ASME. ICONE26, Volume 9: Student Paper Competition, V009T16A035, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81551
https://doi.org/10.1115/ICONE26-81551
View Paper titled, Validation of a Code and Effect of Turbulence Model on Predicting Thermal Stratification Phenomena in the Upper Plenum of SFR
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Topics: Sodium fast reactors, Thermal stratification, Turbulence, Sodium, Momentum, Breeder reactors, Buoyancy, Convection, Deformation, Diffusion (Physics)
Proceedings Papers

Tritium Transport Characteristics Analysis in Molten Salt Reactor Under Transient Conditions

Hao Qin, Chenglong Wang, Suizheng Qiu, Dalin Zhang, Wenxi Tian, Guanghui Su
Proc. ASME. ICONE26, Volume 4: Nuclear Safety, Security, and Cyber Security; Computer Code Verification and Validation, V004T06A023, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81728
https://doi.org/10.1115/ICONE26-81728
View Paper titled, Tritium Transport Characteristics Analysis in Molten Salt Reactor Under Transient Conditions
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Topics: Molten salt reactors, Transients (Dynamics), Absorption, Accidents, Corrosion, Dynamic response, Graphite, High temperature, Steady state
Proceedings Papers

Experimental Studies on the Thermal-Hydraulics of Dowtherm A Through the Pebble Bed With Internal Heat Generation

Limin Liu, Dalin Zhang, Linfeng Li, Yichen Yang, Chenglong Wang, Suizheng Qiu
Proc. ASME. ICONE26, Volume 5: Advanced Reactors and Fusion Technologies; Codes, Standards, Licensing, and Regulatory Issues, V005T05A018, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81917
https://doi.org/10.1115/ICONE26-81917
View Paper titled, Experimental Studies on the Thermal-Hydraulics of Dowtherm A Through the Pebble Bed With Internal Heat Generation
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Topics: Heat, Thermal hydraulics, Fluids, Fuels, Coolants, Flow (Dynamics), High temperature, Convection, Electromagnetic induction, Heating
Proceedings Papers

Numerical Research on Melt Pool Flow Characteristics Under Rolling Condition

Simin Luo, Xin'an Wang, Yapei Zhang, Dalin Zhang, Suizheng Qiu, Guanghui Su
Proc. ASME. ICONE26, Volume 9: Student Paper Competition, V009T16A066, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81994
https://doi.org/10.1115/ICONE26-81994
View Paper titled, Numerical Research on Melt Pool Flow Characteristics Under Rolling Condition
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Topics: Flow (Dynamics), Accidents, China, Computational fluid dynamics, Construction, Heat transfer, Heating, Military systems, Natural convection, Nuclear reactors
Proceedings Papers

Conceptual Design and Neutronics/Thermal-Hydraulic Coupling Optimization Analyses of Two Typical Helium Cooled Solid Breeder Blanket Modules for CFETR Phase II

Shijie Cui, Dalin Zhang, Wenxi Tian, G. H. Su, Suizheng Qiu
Proc. ASME. ICONE26, Volume 5: Advanced Reactors and Fusion Technologies; Codes, Standards, Licensing, and Regulatory Issues, V005T05A012, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81539
https://doi.org/10.1115/ICONE26-81539
View Paper titled, Conceptual Design and Neutronics/Thermal-Hydraulic Coupling Optimization Analyses of Two Typical Helium Cooled Solid Breeder Blanket Modules for CFETR Phase II
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Topics: Conceptual design, Helium, Optimization, China, Design, Energy conversion, Fusion reactors, Power stations, Tokamaks
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

Theoretical and Experimental Research on the Single-Phase and Incipient Boiling Heat Transfer of Liquid Metal Sodium

Dalin Zhang, Jing Chen, Ping Song, Shibao Wang, Xin'an Wang, Linfeng Li, Suizheng Qiu, G. H. Su
Proc. ASME. ICONE25, Volume 5: Advanced and Next Generation Reactors, Fusion Technology; Codes, Standards, Conformity Assessment, Licensing, and Regulatory Issues, V005T05A053, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-67865
https://doi.org/10.1115/ICONE25-67865
View Paper titled, Theoretical and Experimental Research on the Single-Phase and Incipient Boiling Heat Transfer of Liquid Metal Sodium
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Topics: Boiling, Heat transfer, Liquid metals, Sodium, Sodium fast reactors, Annulus, Critical heat flux, Friction, Coolants, Design
Proceedings Papers

Coupled Analysis of Thermal Hydraulics and Neutronics for a Molten Salt Reactor

Jian Ge, Dalin Zhang, Wenxi Tian, Suizheng Qiu, G. H. Su
Proc. ASME. ICONE25, Volume 8: Computational Fluid Dynamics (CFD) and Coupled Codes; Nuclear Education, Public Acceptance and Related Issues, V008T09A036, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-67042
https://doi.org/10.1115/ICONE25-67042
View Paper titled, Coupled Analysis of Thermal Hydraulics and Neutronics for a Molten Salt Reactor
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Topics: Molten salt reactors, Thermal hydraulics, Neutrons, Computational fluid dynamics, Coolants, Design, Diffusion (Physics), Finite volume methods, Momentum, Neutron flux
Proceedings Papers

Experimental Study on the Steam-Water Co-Current Flow Friction Multiplier of the AP1000 Surge Line

Jiangtao Yu, Dalin Zhang, Leitai Shi, Zhiwei Wang, Wenxi Tian, Guanghui Su, Suizheng Qiu
Proc. ASME. ICONE25, Volume 6: Thermal-Hydraulics, V006T08A063, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-66893
https://doi.org/10.1115/ICONE25-66893
View Paper titled, Experimental Study on the Steam-Water Co-Current Flow Friction Multiplier of the AP1000 Surge Line
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Topics: Flow (Dynamics), Friction, Steam, Surges, Water, Pressure drop, Pressure, Accidents, Coolants, Manufacturing
Proceedings Papers

Investigation of the Modified RELAP5 MOD 3.2 Capability to Simulate the Transients of the Fluoride-Salt High-Temperature Reactors

Limin Liu, Qiqi Yan, Dalin Zhang, Suizheng Qiu, G. H. Su
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, V002T06A019, June 26–30, 2016
Publisher: American Society of Mechanical Engineers
Paper No: ICONE24-60429
https://doi.org/10.1115/ICONE24-60429
View Paper titled, Investigation of the Modified RELAP5 MOD 3.2 Capability to Simulate the Transients of the Fluoride-Salt High-Temperature Reactors
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Topics: High temperature, Transients (Dynamics), Accidents, Flow (Dynamics), Fluids, Fuels, Heat, Specific heat, Steady state
Proceedings Papers

Thermo-Hydraulic Analysis of the Optimized Helium Cooled Solid Breeder Blanket for CFETR

Shijie Cui, Dalin Zhang, Jie Chang, Wenxi Tian, Suizheng Qiu, G. H. Su
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, V002T06A008, June 26–30, 2016
Publisher: American Society of Mechanical Engineers
Paper No: ICONE24-60144
https://doi.org/10.1115/ICONE24-60144
View Paper titled, Thermo-Hydraulic Analysis of the Optimized Helium Cooled Solid Breeder Blanket for CFETR
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Topics: Helium, Temperature, Design, Temperature distribution, Ceramics, China, Computational fluid dynamics, Coolants, Cooling, Dynamic analysis
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
Journal Articles

Development of a Thermal-Hydraulic Analysis Code and Transient Analysis for a Fluoride-Salt-Cooled High-Temperature Test Reactor

Yao Xiao, Lin-Wen Hu, Suizheng Qiu, Dalin Zhang, Su Guanghui, Wenxi Tian
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research Papers
ASME J of Nuclear Rad Sci. January 2015, 1(1): 011007.
Paper No: NERS-14-1031
https://doi.org/10.1115/1.4026394
Published Online: February 9, 2015
View Article titled, Development of a Thermal-Hydraulic Analysis Code and Transient Analysis for a Fluoride-Salt-Cooled High-Temperature Test Reactor
Open the PDF for Development of a Thermal-Hydraulic Analysis Code and Transient Analysis for a Fluoride-Salt-Cooled High-Temperature Test Reactor in another window
Topics: Accidents, Coolants, Design, Flow (Dynamics), Fuels, High temperature, Temperature, Transient analysis, Transients (Dynamics), Heat transfer