1-20 of 21
Thermal properties
Close
Save search
Follow your search
Access your saved searches in your account
Would you like to receive an alert when new items match your search?
Close Modal
Sort by
Proceedings Papers

Experimental Study on the Thermal Properties and Stability of Hybrid Nanofluids and Evaluation of its Heat Exchange Efficiency

Yubai Xiao, Hu Zhang, Junmei Wu
Proc. ASME. ICONE2020, Volume 3: Student Paper Competition; Thermal-Hydraulics; Verification and Validation, V003T12A035, August 4–5, 2020
Paper No: ICONE2020-16630
DOI: https://doi.org/10.1115/ICONE2020-16630
View Paper
PDF
Topics: Heat, Nanofluids, Stability, Thermal properties, Water, Thermal conductivity, Heat transfer, Fluids, Accidents, Vessels
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
View Paper
PDF
Topics: Fuels, Composite materials, Light water reactors, Accidents, Nuclear fission, Thermal conductivity, Thermal properties, Cladding systems (Building), Coolants, Enthalpy
Proceedings Papers

The Compatibility of Nuclear Graphite With Molten Salt in the Molten Salt Reactor

Zhoutong He, Hui Tang, Can Zhang, Yantao Gao, Huihao Xia, Xingtai Zhou
Proc. ASME. ICONE26, Volume 2: Plant Systems, Structures, Components, and Materials; Risk Assessments and Management, V002T03A026, July 22–26, 2018
Paper No: ICONE26-82065
DOI: https://doi.org/10.1115/ICONE26-82065
View Paper
PDF
Topics: Graphite, Molten salt reactors, Temperature, Strength (Materials), Thermal expansion, Coolants, Fracture (Materials), Fracture (Process), Irradiation (Radiation exposure), Pressure
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
View Paper
PDF
Topics: Cladding systems (Building), Fuel rods, Light water reactors, Modeling, Fuels, Composite materials, Design, Fibers, Fluence (Radiation measurement), Neutrons
Proceedings Papers

Thermo-Hydraulic Research for Supercritical Water Reactor During Power-Raising Phase of Startup

Li Zichao, Zhou Tao, Zhou Lanyu, Liu Liang, Chen Juan, Yu Hongxing
Proc. ASME. ICONE25, Volume 5: Advanced and Next Generation Reactors, Fusion Technology; Codes, Standards, Conformity Assessment, Licensing, and Regulatory Issues, V005T05A051, July 2–6, 2017
Paper No: ICONE25-67595
DOI: https://doi.org/10.1115/ICONE25-67595
View Paper
PDF
Topics: Supercritical water reactors, Coolants, Temperature, Heat transfer, Feedwater, Flow (Dynamics), Pressure, Security, Thermal properties
Proceedings Papers

Control System Design of Supercritical CO2 Direct Cycle Gas Fast Reactor

Xianshan Zhang, Peiwei Sun
Proc. ASME. ICONE25, Volume 9: Student Paper Competition, V009T15A022, July 2–6, 2017
Paper No: ICONE25-66832
DOI: https://doi.org/10.1115/ICONE25-66832
View Paper
PDF
Topics: Control systems, Cycles, Design, Fast neutron reactors, Supercritical carbon dioxide, Fuels, Manufacturing, Neutrons, Transients (Dynamics), Computer simulation
Proceedings Papers

Investigation of the Effects of Hydrogen Atoms Concentration on the Tungsten Sigma 5 (310) Symmetric Tilt Grain Boundary

Kabiru Atiku, Xue Yang
Proc. ASME. ICONE24, Volume 5: Student Paper Competition, V005T15A030, June 26–30, 2016
Paper No: ICONE24-60450
DOI: https://doi.org/10.1115/ICONE24-60450
View Paper
PDF
Topics: Atoms, Grain boundaries, Hydrogen, Tungsten, Computer software, Isotopes, Modeling, Molecular dynamics, Nuclear fusion, Simulation
Proceedings Papers

Visualization Investigation of Secondary Flow on Heat Transfer Deterioration in Horizontal Heat Tube

Chao Wu, Hui-xiong Li, Qian Zhang
Proc. ASME. ICONE22, Volume 2A: Thermal Hydraulics, V02AT09A062, July 7–11, 2014
Paper No: ICONE22-30477
DOI: https://doi.org/10.1115/ICONE22-30477
View Paper
PDF
Topics: Flow (Dynamics), Heat, Heat transfer, Visualization, Fluids, Buoyancy, Mixed convection, Water, Cooling, Heat conduction
Proceedings Papers

Conjugated Numerical Study on the Performance of Microchannel Heat Sink Using Al 2 O 3 /H 2 O Nanofluid

J. M. Wu, J. Y. Zhao
Proc. ASME. ICONE22, Volume 4: Radiation Protection and Nuclear Technology Applications; Fuel Cycle, Radioactive Waste Management and Decommissioning; Computational Fluid Dynamics (CFD) and Coupled Codes; Reactor Physics and Transport Theory, V004T10A049, July 7–11, 2014
Paper No: ICONE22-31210
DOI: https://doi.org/10.1115/ICONE22-31210
View Paper
PDF
Topics: Heat sinks, Microchannels, Nanofluids, Water, Heat, Control systems, Coolants, Cooling systems, Electronics, Fluids
Proceedings Papers

SCDAP Model Improvement With QUENCH-06 Analysis

Hiroshi Madokoro, Koji Okamoto, Yuki Ishiwatari
Proc. ASME. ICONE22, Volume 5: Innovative Nuclear Power Plant Design and New Technology Application; Student Paper Competition, V005T17A010, July 7–11, 2014
Paper No: ICONE22-30086
DOI: https://doi.org/10.1115/ICONE22-30086
View Paper
PDF
Topics: Accident management, Computers, Electrical resistance, Heat transfer, Light water reactors, Modeling, Oxidation, Temperature profiles, Thermal properties, Uncertainty
Proceedings Papers

Experimental Investigation of Nanotubes Utilization as a Nuclear Fuel Matrix Additive

Jan Varmuza, Karel Katovsky, Jiri Skalicka, Stepan Foral, Jitka Matejkova
Proc. ASME. ICONE22, Volume 5: Innovative Nuclear Power Plant Design and New Technology Application; Student Paper Competition, V005T17A070, July 7–11, 2014
Paper No: ICONE22-31260
DOI: https://doi.org/10.1115/ICONE22-31260
View Paper
PDF
Topics: Nanotubes, Nuclear fuels, Carbon, Nanomaterials, Neutrons, Aluminum, Cladding systems (Building), Composite materials, Fuels, Materials properties
Proceedings Papers

Development and Verification of the Thermal Behavior Analysis Code for MA Containing MOX Fuels

Yoshihisa Ikusawa, Takayuki Ozawa, Shun Hirooka, Koji Maeda, Masato Kato, Seiichiro Maeda
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, V001T02A001, July 7–11, 2014
Paper No: ICONE22-30005
DOI: https://doi.org/10.1115/ICONE22-30005
View Paper
PDF
Topics: Fuels, Irradiation (Radiation exposure), Temperature, Computers, Design methodology, Fast neutron reactors, Melting, Pressure, Thermal conductivity, Thermal properties
Proceedings Papers

Thermal Growth Simulations of the Rotor and Auxiliary Bearing Contact Events

Yulan Zhao, Guojun Yang, Zhengang Shi, Lei Zhao
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, V001T03A001, July 7–11, 2014
Paper No: ICONE22-30053
DOI: https://doi.org/10.1115/ICONE22-30053
View Paper
PDF
Topics: Bearings, Engineering simulation, Rotors, Simulation, Temperature, Heat, Failure, Heat transfer, Ball bearings, Ceramics
Proceedings Papers

Enhanced Thermal Conductivity UO 2 -BeO Fuels Fabrication Methods and Their Thermal Performance in Light Water Reactors

Wenzhong Zhou, Rong Liu
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, V001T02A013, July 7–11, 2014
Paper No: ICONE22-30647
DOI: https://doi.org/10.1115/ICONE22-30647
View Paper
PDF
Topics: Fuels, Light water reactors, Manufacturing, Thermal conductivity, Finite element methods, Nuclear fuels, Composite materials, Computer software, Engineering simulation, Nuclear reactors
Proceedings Papers

Modelling of QUENCH 03 and QUENCH 06 Experiments Using RELAP/SCDAPSIM Code

Tadas Kaliatka, Eugenijus Ušpuras, Algirdas Kaliatka
Proc. ASME. ICONE21, Volume 6: Beyond Design Basis Events; Student Paper Competition, V006T16A020, July 29–August 2, 2013
Paper No: ICONE21-15894
DOI: https://doi.org/10.1115/ICONE21-15894
View Paper
PDF
Topics: Modeling, Accidents, Floods, Light water reactors, Accident management, Computers, Coolants, Electricity (Physics), Fuel rods, Fuels
Proceedings Papers

Effect of Irradiation Deformation and Graphite Varieties on the Irradiation Equivalent Stress and Life of Nuclear Graphite

Xiang Fang, Haitao Wang, Suyuan Yu
Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 5, 697-700, May 17–21, 2010
Paper No: ICONE18-30359
DOI: https://doi.org/10.1115/ICONE18-30359
View Paper
PDF
Topics: Deformation, Graphite, Irradiation (Radiation exposure), Stress, Creep, High temperature, Finite element analysis, Mechanical properties, Neutrons, Thermal properties
Proceedings Papers

Non-Linear Characteristics of Saturated and Subcooled Pool Boiling CHF for Various Test Heater Configuration

Katsuya Fukuda, Qiusheng Liu
Proc. ASME. ICONE17, Volume 3: Thermal Hydraulics; Current Advanced Reactors: Plant Design, Construction, Workforce and Public Acceptance, 247-255, July 12–16, 2009
Paper No: ICONE17-75269
DOI: https://doi.org/10.1115/ICONE17-75269
View Paper
PDF
Topics: Critical heat flux, Heart failure, Pool boiling, Subcooling, Pressure, Cylinders, Hydrodynamic stability, Explosives, Nucleation (Physics), Thermal properties
Proceedings Papers

Adaptation of FEMAXI-6 Code for Fuel Rods of RBMK-1500 and Employment of Uncertainty and Sensitivity Analysis

Tadas Kaliatka, Ausˇra Jusevicˇiu¯te˙, Eugenijus Usˇpuras
Proc. ASME. ICONE17, Volume 4: Codes, Standards, Licensing and Regulatory Issues; Student Paper Competition, 295-301, July 12–16, 2009
Paper No: ICONE17-75110
DOI: https://doi.org/10.1115/ICONE17-75110
View Paper
PDF
Topics: Fuel rods, Sensitivity analysis, Uncertainty, Heat capacity, Thermal analysis, Thermal conductivity, Thermal properties
Proceedings Papers

Analyses of a LBE-Diphyl THT Heat Exchanger With the System Code Trace

Wadim Jaeger, Victor H. Sa´chez Espinoza
Proc. ASME. ICONE16, Volume 4: Structural Integrity; Next Generation Systems; Safety and Security; Low Level Waste Management and Decommissioning; Near Term Deployment: Plant Designs, Licensing, Construction, Workforce and Public Acceptance, 293-300, May 11–15, 2008
Paper No: ICONE16-48073
DOI: https://doi.org/10.1115/ICONE16-48073
View Paper
PDF
Topics: Heat exchangers, Fluids, Temperature, Test facilities, Boundary-value problems, Computational fluid dynamics, Coolants, Design, Flow (Dynamics), Heat transfer
Proceedings Papers

Modeling Cladding-Coolant Heat Transfer of High-Burnup Fuel During RIA

Wenfeng Liu, Mujid S. Kazimi
Proc. ASME. ICONE14, Volume 2: Thermal Hydraulics, 855-864, July 17–20, 2006
Paper No: ICONE14-89829
DOI: https://doi.org/10.1115/ICONE14-89829
View Paper
PDF
Topics: Cladding systems (Building), Coolants, Fuels, Heat transfer, Modeling, Temperature, Film boiling, Critical heat flux, Oxidation, Subcooling