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Proceedings Papers

Numerical Prediction of Flow and Heat Transfer in Supercritical Fluids

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Abdullah Alasif, Andrea Pucciarelli, Osman Siddiqui, Afaque Shams
Proc. ASME. ICONE31, Volume 11: Student Paper Competition, V011T15A050, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-135186
https://doi.org/10.1115/ICONE31-135186
View Paper titled, Numerical Prediction of Flow and Heat Transfer in Supercritical Fluids
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Topics: Computational fluid dynamics, Flow (Dynamics), Generation IV reactors, Heat transfer, Supercritical fluids, Turbulence
Proceedings Papers

Numerical Analysis of Three-Dimensional Flow Field Impact Under Strong Transient Conditions in Advanced Reactors

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Jian Zhao, Jing Zhang, Yingwei Wu, Guanghui Su, Wenxi Tian, Suizheng Qiu
Proc. ASME. ICONE31, Volume 11: Student Paper Competition, V011T15A060, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-135397
https://doi.org/10.1115/ICONE31-135397
View Paper titled, Numerical Analysis of Three-Dimensional Flow Field Impact Under Strong Transient Conditions in Advanced Reactors
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Topics: Accidents, Flow (Dynamics), Numerical analysis, Sodium fast reactors, Transients (Dynamics), Reactor vessels, Pressure, Sodium, Cavities, Vapors
Proceedings Papers

Investigation and Design of Energy-Absorbing Structure in Nuclear Fuel Cask

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Yuchen Hao, Yue Li, Jinhua Wang, Bin Wu, Tao Ma, Haitao Wang
Proc. ASME. ICONE28, Volume 3: Computational Fluid Dynamics (CFD); Verification and Validation; Advanced Methods of Manufacturing (AMM) for Nuclear Reactors and Components; Decontamination, Decommissioning, and Radioactive Waste Management; Beyond Design Basis and Nuclear Safety; Risk Informed Management and Regulation, V003T11A007, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-63388
https://doi.org/10.1115/ICONE28-63388
View Paper titled, Investigation and Design of Energy-Absorbing Structure in Nuclear Fuel Cask
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Topics: Design, Nuclear fuels, Transportation systems, Fuels, Metals, Safety, High temperature, Construction, Containers, Economics
Proceedings Papers

Research on Tritium Behavior Issues in High-Temperature Gas-Cooled Reactors

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Ziling Zhou, Chuan Li, Nan Gui, Feng Xie, Yanwei Wen, Bin Shan, Jia Fu, Qunchao Fan
Proc. ASME. ICONE28, Volume 4: Student Paper Competition, V004T14A016, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-63539
https://doi.org/10.1115/ICONE28-63539
View Paper titled, Research on Tritium Behavior Issues in High-Temperature Gas-Cooled Reactors
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Topics: Diffusion (Physics), Isotopes, Very high temperature reactors, Coolants, Graphite, Absorption, Desorption, Safety, Engineering prototypes, Fuels
Proceedings Papers

Study on the Turbulent Mixed Convection Phenomena Inside the Air-Cooled RCCS Riser

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Dong-Ho Shin, Sin-Yeob Kim, Chan Soo Kim, Goon-Cherl Park, Hyoung Kyu Cho
Proc. ASME. ICONE26, Volume 6B: Thermal-Hydraulics and Safety Analyses, V06BT08A029, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-82071
https://doi.org/10.1115/ICONE26-82071
View Paper titled, Study on the Turbulent Mixed Convection Phenomena Inside the Air-Cooled RCCS Riser
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Topics: Mixed convection, Pipeline risers, Risers (Casting), Turbulence, Ducts, Heat transfer, Cooling systems, Flow (Dynamics), Reactor vessels, Cavities
Proceedings Papers

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

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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

Experimental Nusselt Number in Rod Bundles Cooled by Heavy-Liquid Metals

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J. Pacio, M. Daubner, T. Wetzel, I. Di Piazza, M. Tarantino, D. Martelli, M. Angelucci
Proc. ASME. ICONE26, Volume 6B: Thermal-Hydraulics and Safety Analyses, V06BT08A041, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-82213
https://doi.org/10.1115/ICONE26-82213
View Paper titled, Experimental Nusselt Number in Rod Bundles Cooled by Heavy-Liquid Metals
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Topics: Fuel rods, Metals, Flow (Dynamics), Fuels, Temperature, Coolants, Heat transfer, Thermocouples, Wire, Computer simulation
Proceedings Papers

Research on Thermal Efficiencies of Various Power Cycles for GFRs and VHTRs

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Mohammed Mahdi, Roman Popov, Igor Pioro
Proc. ASME. ICONE26, Volume 9: Student Paper Competition, V009T16A039, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81618
https://doi.org/10.1115/ICONE26-81618
View Paper titled, Research on Thermal Efficiencies of Various Power Cycles for GFRs and VHTRs
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Topics: Thermal efficiency, Thermodynamic power cycles, Very high temperature reactors, Nuclear power stations, Helium, Cycles, Water, Combined cycles, Nitrogen, Gas turbines
Proceedings Papers

Performance Analysis of Generation IV Nuclear Reactor Power Plant Using CO 2 and N 2 : Case Study of a Recuperated Brayton Gas Turbine Cycle

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Emmanuel O. Osigwe, Arnold Gad-Briggs, Theoklis Nikolaidis, Pericles Pilidis, Suresh Sampath
Proc. ASME. ICONE26, Volume 5: Advanced Reactors and Fusion Technologies; Codes, Standards, Licensing, and Regulatory Issues, V005T05A008, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81337
https://doi.org/10.1115/ICONE26-81337
View Paper titled, Performance Analysis of Generation IV Nuclear Reactor Power Plant Using CO 2 and N 2 : Case Study of a Recuperated Brayton Gas Turbine Cycle
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Topics: Carbon dioxide, Cycles, Gas turbines, Generation IV reactors, Power stations, Fluids, Closed-cycle gas turbines, Design, Nitrogen, Nuclear power
Proceedings Papers

Control Scheme Research of 10MW Fluoride Salt Cooled High Temperature Experiment Reactor

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Jian Ruan, Yang Zou, Minghai Li, Hongjie Xu
Proc. ASME. ICONE25, Volume 5: Advanced and Next Generation Reactors, Fusion Technology; Codes, Standards, Conformity Assessment, Licensing, and Regulatory Issues, V005T05A009, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-66228
https://doi.org/10.1115/ICONE25-66228
View Paper titled, Control Scheme Research of 10MW Fluoride Salt Cooled High Temperature Experiment Reactor
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Topics: High temperature, Coolants, Temperature, Flow (Dynamics), Stress, Control equipment, Temperature control, Transient analysis, Transients (Dynamics), Air flow
Proceedings Papers

Thermal-Hydraulic Analysis of the EBR-II SHRT-45R Unprotected Loss of Flow Experiment With Modified RELAP5

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Tang Simiao, Song Jian, Zhang Dalin, Wang Chenglong, Qiu Suizheng, Su Guanghui, Tian Wenxi
Proc. ASME. ICONE25, Volume 5: Advanced and Next Generation Reactors, Fusion Technology; Codes, Standards, Conformity Assessment, Licensing, and Regulatory Issues, V005T05A023, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-66766
https://doi.org/10.1115/ICONE25-66766
View Paper titled, Thermal-Hydraulic Analysis of the EBR-II SHRT-45R Unprotected Loss of Flow Experiment With Modified RELAP5
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Topics: Flow (Dynamics), Sodium fast reactors, Accidents, Feedback, Coolants, Temperature, Fuels, Pumps, Safety, Sodium
Proceedings Papers

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

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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

Calculation of the Macroscopic Group Constant of Pebble Bed Fluoride Salt Cooled High Temperature Reactor Based on the Collision Probability Method

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Dida Zhang, Guobin Jia, Long He, Jiajie Shen, Zhichao Zhan, Hailing Wang, Wei Guo
Proc. ASME. ICONE25, Volume 3: Nuclear Fuel and Material, Reactor Physics and Transport Theory; Innovative Nuclear Power Plant Design and New Technology Application, V003T02A045, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-67194
https://doi.org/10.1115/ICONE25-67194
View Paper titled, Calculation of the Macroscopic Group Constant of Pebble Bed Fluoride Salt Cooled High Temperature Reactor Based on the Collision Probability Method
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Topics: Collisions (Physics), High temperature, Probability, Fuels, Generation IV reactors, Neutron flux
Proceedings Papers

Breeding Properties Study on High Power Thorium Molten Salt Reactor

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Yafen Liu, Rui Guo, Xiangzhou Cai, Rui Yan, Yang Zou, Bo Zhou
Proc. ASME. ICONE25, Volume 5: Advanced and Next Generation Reactors, Fusion Technology; Codes, Standards, Conformity Assessment, Licensing, and Regulatory Issues, V005T05A026, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-66961
https://doi.org/10.1115/ICONE25-66961
View Paper titled, Breeding Properties Study on High Power Thorium Molten Salt Reactor
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Topics: Molten salt reactors, Breeder reactors, Fluids, Fuels, Generation IV reactors, Security, Temperature, Transients (Dynamics)
Proceedings Papers

Numerical Investigation of Spacer Effects on Heat Transfer Enhancement in a Vertical Annular Channel at Supercritical Pressure

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Jinsong Pan, Yao Xiao, Hanyang Gu
Proc. ASME. ICONE25, Volume 8: Computational Fluid Dynamics (CFD) and Coupled Codes; Nuclear Education, Public Acceptance and Related Issues, V008T09A030, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-66911
https://doi.org/10.1115/ICONE25-66911
View Paper titled, Numerical Investigation of Spacer Effects on Heat Transfer Enhancement in a Vertical Annular Channel at Supercritical Pressure
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Topics: Heat transfer, Pressure, Computational fluid dynamics, Fuel rods, Supercritical fluids, Supercritical water reactors, Computer simulation, Economics , Enthalpy, Fluids
Proceedings Papers

Control System Design of Supercritical CO2 Direct Cycle Gas Fast Reactor

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Xianshan Zhang, Peiwei Sun
Proc. ASME. ICONE25, Volume 9: Student Paper Competition, V009T15A022, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-66832
https://doi.org/10.1115/ICONE25-66832
View Paper titled, Control System Design of Supercritical CO2 Direct Cycle Gas Fast Reactor
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Topics: Control systems, Cycles, Design, Fast neutron reactors, Supercritical carbon dioxide, Fuels, Manufacturing, Neutrons, Transients (Dynamics), Computer simulation
Proceedings Papers

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

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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

Modeling and Experiments of a Passive Decay Heat Removal System for Advanced Nuclear Reactors

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Andrea Bersano, Mario De Salve, Cristina Bertani, Nicolò Falcone, Bruno Panella
Proc. ASME. ICONE25, Volume 9: Student Paper Competition, V009T15A054, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-67647
https://doi.org/10.1115/ICONE25-67647
View Paper titled, Modeling and Experiments of a Passive Decay Heat Removal System for Advanced Nuclear Reactors
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Topics: Heat, Modeling, Nuclear reactors, Safety, Condensers (steam plant), Design, Gases, Generation IV reactors, Industrial research, Numerical analysis
Proceedings Papers

Investigation on Creep Mechanisms of Alloy 709

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Abdullah S. Alomari, Nilesh Kumar, Korukonda L. Murty
Proc. ASME. NUCLRF2017, ASME 2017 Nuclear Forum, V009T02A003, June 26–30, 2017
Publisher: American Society of Mechanical Engineers
Paper No: NUCLRF2017-3649
https://doi.org/10.1115/NUCLRF2017-3649
View Paper titled, Investigation on Creep Mechanisms of Alloy 709
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Topics: Alloys, Creep, Stress, Temperature, Grain boundary diffusion, Dislocations, Generation IV reactors, Iron, Mechanical properties, Nuclear reactors
Proceedings Papers

Activities of the Safety and Operation Project for the International Research and Development of the Sodium-Cooled Fast Reactor in the Generation IV International Forum

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Takaaki Sakai, Lixia Ren, Haileyesus Tsige-Tamirat, Alfredo Vasile, Seok-Hun Kang, Yury Ashurko, Thomas Fanning
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, V002T06A021, June 26–30, 2016
Publisher: American Society of Mechanical Engineers
Paper No: ICONE24-60502
https://doi.org/10.1115/ICONE24-60502
View Paper titled, Activities of the Safety and Operation Project for the International Research and Development of the Sodium-Cooled Fast Reactor in the Generation IV International Forum
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Topics: Industrial research, Safety, Sodium fast reactors, Testing, Design, Generation IV reactors, Licensing, Maintenance, Model validation, Nuclear power