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Proceedings Papers

A Sodium-Cooled Thermal-Spectrum Fission Battery

Proc. ASME. ICONE28, Volume 1: Operating Plant Challenges, Successes, and Lessons Learned; Nuclear Plant Engineering; Advanced Reactors and Fusion; Small Modular and Micro-Reactors Technologies and Applications, V001T04A015, August 4–6, 2021

Paper No: ICONE28-65765

DOI: https://doi.org/10.1115/ICONE28-65765

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Topics: Batteries, Nuclear fission, Sodium, Heat, Neutrons, Uranium, Carbon, Data centers, Design, Economics

Proceedings Papers

Heat Transfer and Fluid Flow Characteristic of One Side Heated Vertical Rectangular Channel That Inserted Thin Metallic Wire

Gota Suga, Tetsuaki Takeda

Proc. ASME. ICONE2020, Volume 3: Student Paper Competition; Thermal-Hydraulics; Verification and Validation, V003T12A040, August 4–5, 2020

Paper No: ICONE2020-16705

DOI: https://doi.org/10.1115/ICONE2020-16705

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Topics: Fluid dynamics, Heat transfer, Wire, Very high temperature reactors, Flow (Dynamics), Natural convection, Cooling, Cooling systems, Copper, Gas turbines

Proceedings Papers

Multi-Fluid Gas Turbine Components Scaling for a Generation IV Nuclear Power Plant Performance Simulation

Emmanuel O. Osigwe, Arnold Gad-Briggs, Theoklis Nikolaidis, Pericles Pilidis, Suresh Sampath

Proc. ASME. ICONE26, Volume 9: Student Paper Competition, V009T16A080, July 22–26, 2018

Paper No: ICONE26-82373

DOI: https://doi.org/10.1115/ICONE26-82373

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Topics: Fluids, Gas turbines, Nuclear power stations, Simulation, Closed-cycle gas turbines, Design, Computer simulation, Engineers, Engines

Proceedings Papers

Numerical Simulation of the Performance of an Axial Compressor Operating With Supercritical Carbon Dioxide

Jinlan Gou, Wei Wang, Can Ma, Yong Li, Yuansheng Lin, Huafeng Li

Proc. ASME. ICONE26, Volume 8: Computational Fluid Dynamics (CFD); Nuclear Education and Public Acceptance, V008T09A018, July 22–26, 2018

Paper No: ICONE26-81573

DOI: https://doi.org/10.1115/ICONE26-81573

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Topics: Compressors, Computer simulation, Supercritical carbon dioxide, Flow (Dynamics), Brayton cycle, Fluids, Temperature, Air compressors, Carbon dioxide, Compression

Proceedings Papers

A Combined Small Modular Reactor and Gas Turbine Cycle With Reheat

Robert Stakenborghs, Gregory Kramer

Proc. ASME. ICONE26, Volume 1: Operations and Maintenance, Engineering, Modifications, Life Extension, Life Cycle, and Balance of Plant; Instrumentation and Control (I&C) and Influence of Human Factors; Innovative Nuclear Power Plant Design and SMRs, V001T13A001, July 22–26, 2018

Paper No: ICONE26-81002

DOI: https://doi.org/10.1115/ICONE26-81002

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Topics: Cycles, Gas turbines, Small modular reactors, Power stations, Carbon dioxide, Combined cycle gas turbines, Emissions, Energy generation, Exhaust systems, Fuels

Proceedings Papers

A Concept of Intermediate Heat Exchanger for High-Temperature Gas Reactor Hydrogen and Power Cogeneration System

Noriaki Hirota, Atsuhiko Terada, Xing L. Yan, Kohei Tanaka, Akihito Otani

Paper No: ICONE26-81718

DOI: https://doi.org/10.1115/ICONE26-81718

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Topics: Combined heat and power, Heat exchangers, High temperature, Hydrogen, Nuclear reactors, Conceptual design, Design, Gas turbines, Construction, Creep

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

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

Paper No: ICONE26-81337

DOI: https://doi.org/10.1115/ICONE26-81337

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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

A Review of Brayton Helium Gas Turbine Cycles for GFR and VHTR Generation IV Nuclear Power Plants

Arnold Gad-Briggs, Pericles Pilidis, Theoklis Nikolaidis

Proc. ASME. ICONE26, Volume 5: Advanced Reactors and Fusion Technologies; Codes, Standards, Licensing, and Regulatory Issues, V005T05A013, July 22–26, 2018

Paper No: ICONE26-81681

DOI: https://doi.org/10.1115/ICONE26-81681

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Topics: Cycles, Gas turbines, Helium, Nuclear power stations, Very high temperature reactors, Coolants, Design, Temperature, Fast neutron reactors

Proceedings Papers

A Framework and Model for Assessing the Design Point Performance, Off-Design Point Performance, Control, Economics and Risks of Brayton Helium Gas Turbine Cycles for Generation IV Nuclear Power Plants

Arnold Gad-Briggs, Pericles Pilidis, Theoklis Nikolaidis

Proc. ASME. ICONE26, Volume 5: Advanced Reactors and Fusion Technologies; Codes, Standards, Licensing, and Regulatory Issues, V005T05A014, July 22–26, 2018

Paper No: ICONE26-81686

DOI: https://doi.org/10.1115/ICONE26-81686

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Topics: Cycles, Design, Economics , Gas turbines, Helium, Nuclear power stations, Temperature, Decision making, Pressure, Stress

Proceedings Papers

Heat Transfer and Fluid Flow Characteristics of One Side Heated Vertical Rectangular Channel Applied As Vessel Cooling System of VHTR

Kenta Fujikami, Tetsuaki Takeda, Shumpei Funatani

Proc. ASME. ICONE26, Volume 9: Student Paper Competition, V009T16A046, July 22–26, 2018

Paper No: ICONE26-81700

DOI: https://doi.org/10.1115/ICONE26-81700

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Topics: Cooling systems, Fluid dynamics, Heat transfer, Very high temperature reactors, Vessels, Flow (Dynamics), Natural convection, Porosity, Porous materials, Cooling

Proceedings Papers

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

Mohammed Mahdi, Roman Popov, Igor Pioro

Proc. ASME. ICONE26, Volume 9: Student Paper Competition, V009T16A039, July 22–26, 2018

Paper No: ICONE26-81618

DOI: https://doi.org/10.1115/ICONE26-81618

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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

Analysis of Loss-of-Flow Accidents in Pre-Cooler and Inter-Cooler of HTR-10GT

Xiaoyong Yang, Xiao Li, Jie Wang, Youjie Zhang

Proc. ASME. NUCLRF2018, ASME 2018 Nuclear Forum, V001T04A001, June 24–28, 2018

Paper No: NUCLRF2018-7381

DOI: https://doi.org/10.1115/NUCLRF2018-7381

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Topics: Accidents, Flow (Dynamics), Helium, Temperature, Water, Water temperature, Heat exchangers, Safety, Very high temperature reactors, Brayton cycle

Proceedings Papers

Analyses of Off-Design Point Performances of Simple and Intercooled Brayton Helium Recuperated Gas Turbine Cycles for Generation IV Nuclear Power Plants

Arnold Gad-Briggs, Pericles Pilidis

Proc. ASME. ICONE25, Volume 9: Student Paper Competition, V009T15A055, July 2–6, 2017

Paper No: ICONE25-67714

DOI: https://doi.org/10.1115/ICONE25-67714

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Topics: Cycles, Design, Gas turbines, Helium, Nuclear power stations, Pressure, Flow (Dynamics), Stress, Compressors, Temperature

Proceedings Papers

Analyses of the Off-Design Point Performance of a High Pressure Ratio Intercooled Brayton Helium Gas Turbine Cycle for Generation IV Nuclear Power Plants

Arnold Gad-Briggs, Pericles Pilidis

Proc. ASME. ICONE25, Volume 9: Student Paper Competition, V009T15A056, July 2–6, 2017

Paper No: ICONE25-67715

DOI: https://doi.org/10.1115/ICONE25-67715

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Topics: Cycles, Design, Gas turbines, Helium, High pressure (Physics), Nuclear power stations, Pressure, Stress, Very high temperature reactors, Compressors

Proceedings Papers

Reinforcement of Emergency Power Supply System for Next Generation SFR

Nobuyuki Ishikawa, Yoshitaka Chikazawa, Daisuke Sato, Risako Ikari

Proc. ASME. ICONE25, Volume 5: Advanced and Next Generation Reactors, Fusion Technology; Codes, Standards, Conformity Assessment, Licensing, and Regulatory Issues, V005T05A038, July 2–6, 2017

Paper No: ICONE25-67369

DOI: https://doi.org/10.1115/ICONE25-67369

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Topics: Emergency power, Sodium fast reactors, Design, Generators, Cooling systems, Emergencies, Optimization, Accidents, Diesel generators, Fuels

Proceedings Papers

Heat Transfer Characteristics of Downward Facing Hot Horizontal Surfaces Using Mist Jet Impingement

Ashutosh Kumar Yadav, Parantak Sharma, Avadhesh Kumar Sharma, Mayank Modak, Vishal Nirgude, Santosh K. Sahu

Proc. ASME. ICONE25, Volume 6: Thermal-Hydraulics, V006T08A099, July 2–6, 2017

Paper No: ICONE25-67537

DOI: https://doi.org/10.1115/ICONE25-67537

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Topics: Heat transfer, Cooling, Water, Emergency core cooling systems, Heat flux, Impingement cooling, Nozzles, Sprays, Steel, Accidents

Proceedings Papers

Nuclear Systems for a Low Carbon Electrical Grid

Nima Fathi, Patrick McDaniel, Charles Forsberg, Cassiano de Oliveira

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, V001T03A007, June 26–30, 2016

Paper No: ICONE24-60128

DOI: https://doi.org/10.1115/ICONE24-60128

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Topics: Carbon, Power grids, Hydrogen, Co-firing, Combined cycles, Electric power generation, Gas turbines, Nuclear power stations, Renewable energy, Storage

Proceedings Papers

Flowsheet Study of a Multistage Flash Desalination System for Cogeneration With High Temperature Gas-Cooled Reactor

Yu Kamiji, Hiroki Noguchi, Atsuhiko Terada, Xing Yan

Proc. ASME. ICONE22, Volume 3: Next Generation Reactors and Advanced Reactors; Nuclear Safety and Security, V003T05A005, July 7–11, 2014

Paper No: ICONE22-30142

DOI: https://doi.org/10.1115/ICONE22-30142

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Topics: Combined heat and power, Very high temperature reactors, Water, Heat, Waste heat, Heat recovery, Cycles, Energy generation, Gas turbines, Heat transfer

Proceedings Papers

Study on Neutronics and Thermalhydraulics Characteristics of 1200-MW el Pressure-Channel SuperCritical Water-Cooled Reactor (SCWR)

Marija Miletic, Wargha Peiman, Amjad Farah, Jeffrey Samuel, Alexey Dragunov

Proc. ASME. ICONE22, Volume 5: Innovative Nuclear Power Plant Design and New Technology Application; Student Paper Competition, V005T17A007, July 7–11, 2014

Paper No: ICONE22-30040

DOI: https://doi.org/10.1115/ICONE22-30040

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Topics: Pressure, Supercritical water reactors, Water, Thermal efficiency, Nuclear power stations, Coal, Fuels, Heat transfer, Power stations, Turbines

Proceedings Papers

A Study on Performance Characteristics for Closed Brayton Cycle in Inventory Regulation

Huijing Jiang, Xiaoyong Yang, Ming Ding, Jie Wang

Proc. ASME. ICONE22, Volume 2B: Thermal Hydraulics, V02BT09A013, July 7–11, 2014

Paper No: ICONE22-30674

DOI: https://doi.org/10.1115/ICONE22-30674

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Topics: Brayton cycle, Performance characterization, Cycles, Helium, Pressure, Flow (Dynamics), Gas turbines, Heat exchangers, High temperature, Temperature

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NARROW

A Sodium-Cooled Thermal-Spectrum Fission Battery

Heat Transfer and Fluid Flow Characteristic of One Side Heated Vertical Rectangular Channel That Inserted Thin Metallic Wire

Multi-Fluid Gas Turbine Components Scaling for a Generation IV Nuclear Power Plant Performance Simulation

Numerical Simulation of the Performance of an Axial Compressor Operating With Supercritical Carbon Dioxide

A Combined Small Modular Reactor and Gas Turbine Cycle With Reheat

A Concept of Intermediate Heat Exchanger for High-Temperature Gas Reactor Hydrogen and Power Cogeneration System

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

A Review of Brayton Helium Gas Turbine Cycles for GFR and VHTR Generation IV Nuclear Power Plants

A Framework and Model for Assessing the Design Point Performance, Off-Design Point Performance, Control, Economics and Risks of Brayton Helium Gas Turbine Cycles for Generation IV Nuclear Power Plants

Heat Transfer and Fluid Flow Characteristics of One Side Heated Vertical Rectangular Channel Applied As Vessel Cooling System of VHTR

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

Analysis of Loss-of-Flow Accidents in Pre-Cooler and Inter-Cooler of HTR-10GT

Analyses of Off-Design Point Performances of Simple and Intercooled Brayton Helium Recuperated Gas Turbine Cycles for Generation IV Nuclear Power Plants

Analyses of the Off-Design Point Performance of a High Pressure Ratio Intercooled Brayton Helium Gas Turbine Cycle for Generation IV Nuclear Power Plants

Reinforcement of Emergency Power Supply System for Next Generation SFR

Heat Transfer Characteristics of Downward Facing Hot Horizontal Surfaces Using Mist Jet Impingement

Nuclear Systems for a Low Carbon Electrical Grid

Flowsheet Study of a Multistage Flash Desalination System for Cogeneration With High Temperature Gas-Cooled Reactor

Study on Neutronics and Thermalhydraulics Characteristics of 1200-MW el Pressure-Channel SuperCritical Water-Cooled Reactor (SCWR)

A Study on Performance Characteristics for Closed Brayton Cycle in Inventory Regulation

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