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Proceedings Papers

A Transient Model of Sodium Heat Pipe With Phase Change Temperature Difference

Ruicheng Zhong, Yugao Ma, Qingzhu Zhao, Jian Deng, Yu Liu, Shuhua Ding

Proc. ASME. ICONE29, Volume 15: Student Paper Competition, V015T16A085, August 8–12, 2022

Paper No: ICONE29-92202

DOI: https://doi.org/10.1115/ICONE29-92202

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Topics: Condensation, Evaporation, Flow (Dynamics), Heat pipes, Sodium, Temperature, Thermal resistance, Transients (Dynamics), Steady state, Heat transfer

Proceedings Papers

A Finnish District Heating Reactor: Neutronics Design and Fuel Cycle Simulations

Jaakko Leppänen, Ville Valtavirta, Riku Tuominen, Antti Rintala, Unna Lauranto

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, V001T04A010, August 4–6, 2021

Paper No: ICONE28-64347

DOI: https://doi.org/10.1115/ICONE28-64347

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Topics: Central heating, Design, Engineering simulation, Nuclear fuel cycle, Simulation, Fuels, Boron, Cycles, Heating, Operating temperature

Proceedings Papers

Stress Analysis of the Pressurized-Water Reactor Control Rod Under Operating Conditions

Leo A. Carrilho

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, V001T05A015, August 4–5, 2020

Paper No: ICONE2020-16872

DOI: https://doi.org/10.1115/ICONE2020-16872

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Topics: Pressurized water reactors, Stress, Stress analysis (Engineering), Water, Cladding systems (Building), Finite element model, Fluence (Radiation measurement), Temperature, Thermal expansion, Coolants

Proceedings Papers

Computational Simulation of Hydrogen Permeation Experiment

Xiao Wu, WaiLam Chan, Shanbin Shi, Xiaodong Sun, Richard Christensen

Proc. ASME. ICONE26, Volume 9: Student Paper Competition, V009T16A092, July 22–26, 2018

Paper No: ICONE26-82487

DOI: https://doi.org/10.1115/ICONE26-82487

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Topics: Hydrogen, Simulation, Cross-flow, Coolants, Simulation results, Design, Experimental design, Gas chromatography, Gas flow, Gases

Proceedings Papers

Prediction of Performance of Multi-Stage Orifice Assembly Using CFD Code

Kalyan K. Niyogi, Stefan Anton, Debabrata Mitra-Majumdar

Proc. ASME. ICONE26, Volume 8: Computational Fluid Dynamics (CFD); Nuclear Education and Public Acceptance, V008T09A005, July 22–26, 2018

Paper No: ICONE26-81186

DOI: https://doi.org/10.1115/ICONE26-81186

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Topics: Computational fluid dynamics, Manufacturing, Flow (Dynamics), Design, Cavitation, Fluids, Pressure, Pressure drop, Engineering prototypes, Nuclear power stations

Proceedings Papers

Structural Integrity Assessment to Justify Increase in Upper Operating Temperature Limit of AGR Dome

Antony M. Hurst

Proc. ASME. ICONE25, Volume 2: Plant Systems, Structures, Components and Materials, V002T03A067, July 2–6, 2017

Paper No: ICONE25-66859

DOI: https://doi.org/10.1115/ICONE25-66859

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Topics: Domes (Structural elements), Operating temperature, Temperature, Failure, Creep, Safety, Welded joints, Diaphragms (Mechanical devices), Diaphragms (Structural), Failure mechanisms

Proceedings Papers

Sealing Structure Design for Normal Residual Heat Removal Exchanger

Xilin Li, Ming Jiao

Proc. ASME. ICONE25, Volume 2: Plant Systems, Structures, Components and Materials, V002T03A046, July 2–6, 2017

Paper No: ICONE25-66424

DOI: https://doi.org/10.1115/ICONE25-66424

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Topics: Design, Heat, Sealing (Process), Gaskets, Metals, Pressure, Shells, Accidents, Flanges, High pressure (Physics)

Proceedings Papers

Research on Nickel-Plated Hydrogen-Absorption Device in Fuel Rod and Performance Testing

Zhou Qin, Li Jiwei, Dang Yu, Ding Yang

Proc. ASME. ICONE25, Volume 3: Nuclear Fuel and Material, Reactor Physics and Transport Theory; Innovative Nuclear Power Plant Design and New Technology Application, V003T02A041, July 2–6, 2017

Paper No: ICONE25-67112

DOI: https://doi.org/10.1115/ICONE25-67112

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Topics: Absorption, Fuel rods, Hydrogen, Nickel plating, Testing performance, Cladding systems (Building), Design, Pressure, Zirconium, Alloys

Proceedings Papers

An Innovative Spherical Fuel Element to Inhibit the Infiltration of Liquid Fluoride Salt in Molten Salt Reactor

Yajuan Zhong, Jun Lin, Liujun Xu, Haitao Jiang, Zhiyong Zhu

Proc. ASME. ICONE25, Volume 3: Nuclear Fuel and Material, Reactor Physics and Transport Theory; Innovative Nuclear Power Plant Design and New Technology Application, V003T02A023, July 2–6, 2017

Paper No: ICONE25-66639

DOI: https://doi.org/10.1115/ICONE25-66639

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Topics: Fuels, Molten salt reactors, Graphite, Shells, Density, Stress, Design, Operating temperature, Porosity, Safety

Proceedings Papers

Modeling and Thermal Calculation of Fuel Rod With SiC f /SiC Cladding for LWRs

Shang Xinyuan, Zhang Shaoyang, Zhang Aimin

Proc. ASME. ICONE25, Volume 3: Nuclear Fuel and Material, Reactor Physics and Transport Theory; Innovative Nuclear Power Plant Design and New Technology Application, V003T02A040, July 2–6, 2017

Paper No: ICONE25-67078

DOI: https://doi.org/10.1115/ICONE25-67078

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Topics: Cladding systems (Building), Fuel rods, Light water reactors, Modeling, Fuels, Composite materials, Design, Fibers, Fluence (Radiation measurement), Neutrons

Proceedings Papers

Flow Field Analysis of the Reactor Coolant Pump Internal Cooling Circulation

Jie Qin, Qingmu Xu, Junkai Yuan, Kun Cai

Proc. ASME. ICONE25, Volume 8: Computational Fluid Dynamics (CFD) and Coupled Codes; Nuclear Education, Public Acceptance and Related Issues, V008T09A040, July 2–6, 2017

Paper No: ICONE25-67179

DOI: https://doi.org/10.1115/ICONE25-67179

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Topics: Cooling, Flow (Dynamics), Nuclear reactor coolants, Pumps, Bearings, Engines, Motors, Flywheels, Heat, Heat transfer

Proceedings Papers

Conceptual Design for CHP System for Class III Power

Vajran Sarvendran, Heli Patel, Glenn Harvel

Proc. ASME. ICONE25, Volume 9: Student Paper Competition, V009T15A049, July 2–6, 2017

Paper No: ICONE25-67575

DOI: https://doi.org/10.1115/ICONE25-67575

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Topics: Cogeneration systems, Conceptual design, Fuels, Nuclear power stations, Combined heat and power, Absorption, Coolers, Diesel generators, Emergency power, Fluids

Proceedings Papers

Data Processing Method for Effective Thermal Diffusivity Experiment of Pebble Bed in High Temperature Gas-Cooled Reactors

Yongyong Wu, Cheng Ren, Rui Li, Pengxin Cheng, Xingtuan Yang, Jiyuan Tu

Proc. ASME. ICONE25, Volume 6: Thermal-Hydraulics, V006T08A003, July 2–6, 2017

Paper No: ICONE25-66053

DOI: https://doi.org/10.1115/ICONE25-66053

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Topics: Thermal diffusivity, Very high temperature reactors, Temperature, Algorithms, Construction, Electrical conductivity, Heat transfer, High temperature, Operating temperature, Robustness

Proceedings Papers

Supercritical CO2 Power Cycle for Small Modular Reactor

Zhangpeng Guo, Yang Zhao, Fenglei Niu, Daogang Lu

Proc. ASME. ICONE25, Volume 6: Thermal-Hydraulics, V006T08A005, July 2–6, 2017

Paper No: ICONE25-66103

DOI: https://doi.org/10.1115/ICONE25-66103

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Topics: Small modular reactors, Supercritical carbon dioxide, Thermodynamic power cycles, Turbines, Cycles, Pressure, Temperature, Thermal efficiency, Nuclear power stations, Steam

Proceedings Papers

Heat Transfer Simulation of the Fuel Transport Cask for Spherical Fuel Elements in Molten Salt Reactor

Yang Liu, Jun Wang

Proc. ASME. ICONE24, Volume 3: Thermal-Hydraulics, V003T09A047, June 26–30, 2016

Paper No: ICONE24-60633

DOI: https://doi.org/10.1115/ICONE24-60633

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Topics: Fuels, Heat transfer, Molten salt reactors, Simulation, Accidents, Boiling water reactors, Design, Operating temperature, Pressurized water reactors, Radiation (Physics)

Proceedings Papers

The ATWS Analysis of One Control Rod Withdrawal Out of the HTR-10GT Core Under the Loss of the System Pressure

Minggang Lang

Proc. ASME. ICONE22, Volume 2A: Thermal Hydraulics, V02AT09A002, July 7–11, 2014

Paper No: ICONE22-30015

DOI: https://doi.org/10.1115/ICONE22-30015

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Topics: Pressure, Temperature, Accidents, Scram, Design, Errors, Fuels, Gas turbines, Boilers, Cavities

Proceedings Papers

The Study and Development of Excitation Source for Sensors of the AMB System in HTGR

Xiaohan Liu, Ni Mo

Proc. ASME. ICONE22, Volume 6: Nuclear Education, Public Acceptance and Related Issues; Instrumentation and Controls (I&C); Fusion Engineering; Beyond Design Basis Events, V006T13A014, July 7–11, 2014

Paper No: ICONE22-30920

DOI: https://doi.org/10.1115/ICONE22-30920

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Topics: Excitation, Sensors, Very high temperature reactors, Helium, Magnetic bearings, Active damping, Bearings, China, Circuits, Design

Proceedings Papers

Zirconium Dioxide as a Protective Layer of Zirconium Fuel Cladding

Barbora Benešová, Radek Škoda

Proc. ASME. ICONE22, Volume 1: Plant Operations, Maintenance, Engineering, Modifications, Life Cycle and Balance of Plant; Nuclear Fuel and Materials; Plant Systems, Structures and Components; Codes, Standards, Licensing and Regulatory Issues, V001T02A018, July 7–11, 2014

Paper No: ICONE22-30848

DOI: https://doi.org/10.1115/ICONE22-30848

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Topics: Cladding systems (Building), Fuels, Zirconium, Oxidation, Stress, Temperature, Accidents, Ceramics, Cooling, Corrosion

Proceedings Papers

Thermal-Hydraulic and Neutronic Analysis of a Re-Entrant Fuel Channel Design for Pressure-Channel Supercritical Water-Cooled Reactors

W. Peiman, I. Pioro, K. Gabriel

Proc. ASME. ICONE22, Volume 5: Innovative Nuclear Power Plant Design and New Technology Application; Student Paper Competition, V005T17A044, July 7–11, 2014

Paper No: ICONE22-30614

DOI: https://doi.org/10.1115/ICONE22-30614

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Topics: Design, Fuels, Pressure, Water, Supercritical water reactors, Temperature, Nuclear reactors, Coolants, Thermal efficiency, Boiling water reactors

Proceedings Papers

Neutronics Studies on a Generic Pressure-Channel Reactor With Nuclear Steam Superheat

Matthew Baldock, Wargha Peiman, Andrei Vincze, Rand Abdullah, Khalil Sidawi, Igor Pioro

Proc. ASME. ICONE22, Volume 5: Innovative Nuclear Power Plant Design and New Technology Application; Student Paper Competition, V005T17A017, July 7–11, 2014

Paper No: ICONE22-30135

DOI: https://doi.org/10.1115/ICONE22-30135

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Topics: Pressure, Steam, Coolants, Temperature, Design, Fuels, Nuclear power stations, Pressure vessels, Pressurized water reactors, Thermal efficiency

NARROW

A Transient Model of Sodium Heat Pipe With Phase Change Temperature Difference

A Finnish District Heating Reactor: Neutronics Design and Fuel Cycle Simulations

Stress Analysis of the Pressurized-Water Reactor Control Rod Under Operating Conditions

Computational Simulation of Hydrogen Permeation Experiment

Prediction of Performance of Multi-Stage Orifice Assembly Using CFD Code

Structural Integrity Assessment to Justify Increase in Upper Operating Temperature Limit of AGR Dome

Sealing Structure Design for Normal Residual Heat Removal Exchanger

Research on Nickel-Plated Hydrogen-Absorption Device in Fuel Rod and Performance Testing

An Innovative Spherical Fuel Element to Inhibit the Infiltration of Liquid Fluoride Salt in Molten Salt Reactor

Modeling and Thermal Calculation of Fuel Rod With SiC f /SiC Cladding for LWRs

Flow Field Analysis of the Reactor Coolant Pump Internal Cooling Circulation

Conceptual Design for CHP System for Class III Power

Data Processing Method for Effective Thermal Diffusivity Experiment of Pebble Bed in High Temperature Gas-Cooled Reactors

Supercritical CO2 Power Cycle for Small Modular Reactor

Heat Transfer Simulation of the Fuel Transport Cask for Spherical Fuel Elements in Molten Salt Reactor

The ATWS Analysis of One Control Rod Withdrawal Out of the HTR-10GT Core Under the Loss of the System Pressure

The Study and Development of Excitation Source for Sensors of the AMB System in HTGR

Zirconium Dioxide as a Protective Layer of Zirconium Fuel Cladding

Thermal-Hydraulic and Neutronic Analysis of a Re-Entrant Fuel Channel Design for Pressure-Channel Supercritical Water-Cooled Reactors

Neutronics Studies on a Generic Pressure-Channel Reactor With Nuclear Steam Superheat

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