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Journal Articles

Heat Flux Correlations for Condensation From Steam and Air Mixtures on Vertical Flat Plates

Available to Purchase
Michio Murase, Toshiya Takaki
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2025, 11(2): 021401.
Paper No: NERS-24-1021
https://doi.org/10.1115/1.4066343
Published Online: October 8, 2024
View Articletitled, Heat Flux Correlations for Condensation From Steam and Air Mixtures on Vertical Flat Plates
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Topics: Condensation, Flat plates, Heat, Heat flux, Natural convection
Journal Articles

Validation Assessment of Turbulent Reacting Flow Model Using the Area-Validation Metric on Medium-Scale Methanol Pool Fire Results

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Jared Kirsch, Nima Fathi
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2024, 10(4): 041701.
Paper No: NERS-23-1014
https://doi.org/10.1115/1.4065173
Published Online: May 10, 2024
View Articletitled, Validation Assessment of Turbulent Reacting Flow Model Using the Area-Validation Metric on Medium-Scale Methanol Pool Fire Results
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Topics: Fire, Flames, Flow (Dynamics), Heat flux, Liquid pool fires, Methanol, Simulation, Temperature, Turbulence, Combustion
Journal Articles

An Improved Heat Flux Partitioning Model of Nucleate Boiling Under Saturated Pool Boiling Condition

Free
Mingfu He, Minghui Chen
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2024, 10(3): 031401.
Paper No: NERS-23-1093
https://doi.org/10.1115/1.4064337
Published Online: April 17, 2024
View Articletitled, An Improved Heat Flux Partitioning Model of Nucleate Boiling Under Saturated Pool Boiling Condition
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Topics: Bubbles, Dynamics (Mechanics), Heat flux, Heat transfer, Nucleate boiling, Pool boiling, Boiling, Nucleation (Physics), Quenching (Metalworking), Critical heat flux
Journal Articles

Numerical Verifications on Heat Transfer to Supercritical Water Flowing Upward in a 4-m Long Bare Vertical Tube

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Dong Yang, Jiaxiang Chen, Yongchang Feng, Lin Chen
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2022, 8(2): 021402.
Paper No: NERS-20-1194
https://doi.org/10.1115/1.4051248
Published Online: October 19, 2021
View Articletitled, Numerical Verifications on Heat Transfer to Supercritical Water Flowing Upward in a 4-m Long Bare Vertical Tube
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Topics: Heat transfer, Turbulence, Water, Temperature, Computer simulation, Heat flux, Heat, Density, Flow (Dynamics), Viscosity
Journal Articles

Experimental Investigation of the Transient Pool Boiling Heat Transfer on the Quenching of Vertical Rodlet in Water

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Zefeng Wang, Jian Deng, Zhifang Qiu, Xiaoyu Wang, Lei Zhong, Mingjun Zhong
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2022, 8(2): 021403.
Paper No: NERS-20-1202
https://doi.org/10.1115/1.4051875
Published Online: October 19, 2021
View Articletitled, Experimental Investigation of the Transient Pool Boiling Heat Transfer on the Quenching of Vertical Rodlet in Water
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Topics: Film boiling, Heat flux, Heat transfer, Pool boiling, Quenching (Metalworking), Temperature, Transients (Dynamics), Water, Heat conduction, Heat transfer coefficients
Journal Articles

Computational Fluid Dynamic Analysis of the ESFR Reactor Pit Cooling System in Case of Sodium Leakage

Open Access
Aleksander Grah, Haileyesus Tsige-Tamirat, Joel Guidez, Antoine Gerschenfeld, Konstantin Mikityuk, Janos Bodi, Enrico Girardi
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2022, 8(1): 011314.
Paper No: NERS-20-1204
https://doi.org/10.1115/1.4051292
Published Online: September 20, 2021
View Articletitled, Computational Fluid Dynamic Analysis of the ESFR Reactor Pit Cooling System in Case of Sodium Leakage
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Topics: Computational fluid dynamics, Concretes, Cooling, Cooling systems, Design, Heat, Heat flux, Leakage, Reactor vessels, Safety
Journal Articles

Heat Transfer in Supercritical Fluids: A Review

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Kapil Bodkha, N. K. Maheshwari
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Review Articles
ASME J of Nuclear Rad Sci. July 2021, 7(3): 030802.
Paper No: NERS-20-1029
https://doi.org/10.1115/1.4048898
Published Online: February 19, 2021
View Articletitled, Heat Transfer in Supercritical Fluids: A Review
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Topics: Carbon dioxide, Fluids, Heat transfer, Supercritical fluids, Temperature, Water, Pressure, Heat flux
Journal Articles

Heat Transfer in Induction Melting of Aluminum Oxide in Cold Crucible

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David Rot, Jan Hrbek, Jakub Jirinec
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2021, 7(2): 021602.
Paper No: NERS-20-1147
https://doi.org/10.1115/1.4048899
Published Online: November 16, 2020
View Articletitled, Heat Transfer in Induction Melting of Aluminum Oxide in Cold Crucible
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Topics: Aluminum, Cooling, Design, Electromagnetic induction, Heat transfer, Melting, Temperature, Water, Inductors, Heat flux
Journal Articles

Manipulation System for Measuring Heat Flux in Radioactive Melt

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Michal Knedlík, David Rot, Jan Hrbek
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2021, 7(2): 021801.
Paper No: NERS-20-1140
https://doi.org/10.1115/1.4048632
Published Online: October 30, 2020
View Articletitled, Manipulation System for Measuring Heat Flux in Radioactive Melt
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Topics: Control algorithms, Electromagnetic induction, Heat flux, Manipulators, Melting, Safety, Temperature, Testing, User interfaces, Computer software
Journal Articles

A Simplified Two-Group Multipoint Kinetics Model

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Santosh K. Pradhan, K. Obaidurrahman, Kannan N. Iyer
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2021, 7(1): 011502.
Paper No: NERS-19-1155
https://doi.org/10.1115/1.4046254
Published Online: October 1, 2020
View Articletitled, A Simplified Two-Group Multipoint Kinetics Model
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Topics: Eigenvalues, Heat flux, Neutrons, Steady state, Transients (Dynamics), Thermal hydraulics, Diffusion (Physics), Simulation, Circuits, Fluid dynamics
Journal Articles

Steam Condensation Heat Transfer During Initial Blow-Down Period of a Severe Nuclear Accident

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Mahesh Kumar Yadav, Maneesh Punetha, Abhinav Bhanawat, Sameer Khandekar, Pavan K. Sharma
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2020, 6(4): 041108.
Paper No: NERS-19-1164
https://doi.org/10.1115/1.4046910
Published Online: September 4, 2020
View Articletitled, Steam Condensation Heat Transfer During Initial Blow-Down Period of a Severe Nuclear Accident
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Topics: Accidents, Condensation, Heat flux, Heat transfer, Pressure, Steady state, Steam, Temperature, Transients (Dynamics), Containment
Journal Articles

Investigations on Effect of Lift and Wall Lubrication Forces on the Subcooled Flow Boiling

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Sai Raja Gopal Vadlamudi, Arun K. Nayak
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2020, 6(4): 041109.
Paper No: NERS-19-1165
https://doi.org/10.1115/1.4048124
Published Online: September 4, 2020
View Articletitled, Investigations on Effect of Lift and Wall Lubrication Forces on the Subcooled Flow Boiling
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Topics: Boiling, Bubbles, Flow (Dynamics), Lift (Fluid dynamics), Lubrication, Porosity, Subcooling, Turbulence, Heat flux
Journal Articles

Experimental Validation of ANSYS CFX for Transient Flows With Heat Transfer in a Tubular Heat Exchanger

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Angel Papukchiev
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2020, 6(2): 021104.
Paper No: NERS-19-1029
https://doi.org/10.1115/1.4045074
Published Online: January 29, 2020
View Articletitled, Experimental Validation of ANSYS CFX for Transient Flows With Heat Transfer in a Tubular Heat Exchanger
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Topics: Flow (Dynamics), Fluids, Heat exchangers, Heat transfer, Modeling, Simulation, Temperature, Transients (Dynamics), Turbulence, Computational fluid dynamics
Journal Articles

Sensitivity Analysis of the Thermal Diffusion Coefficient Effect on the Departure From Nucleate Boiling Ratio With the VIPRE Code

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Rosario Delgado-Tardáguila, Marisol Corisco, Antonio Espejo, Daniel Navarro, Javier Riverola
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2019, 5(2): 020909.
Paper No: NERS-18-1057
https://doi.org/10.1115/1.4042358
Published Online: March 15, 2019
View Articletitled, Sensitivity Analysis of the Thermal Diffusion Coefficient Effect on the Departure From Nucleate Boiling Ratio With the VIPRE Code
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Topics: Design, Fuels, Nucleate boiling, Thermal diffusion, Turbulence, Enthalpy, Momentum, Heat flux, Flow (Dynamics), Sensitivity analysis
Journal Articles

Coupling of a Reactor Analysis Code and a Lower Head Thermal Analysis Solver

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Hiroshi Madokoro, Alexei Miassoedov, Thomas Schulenberg
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2019, 5(1): 011017.
Paper No: NERS-18-1035
https://doi.org/10.1115/1.4041278
Published Online: January 24, 2019
View Articletitled, Coupling of a Reactor Analysis Code and a Lower Head Thermal Analysis Solver
Open the PDF for Coupling of a Reactor Analysis Code and a Lower Head Thermal Analysis Solver in another window
Topics: Cooling, Heat, Heat transfer, Temperature, Thermal analysis, Vessels, Heating, Accidents, Water, Heat flux
Journal Articles

Numerical Investigation of Convective Heat Transfer to Supercritical Pressure Hydrogen in a Straight Tube

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Yu Ji, Jun Sun, Lei Shi
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2018, 4(3): 031012.
Paper No: NERS-17-1193
https://doi.org/10.1115/1.4039600
Published Online: May 16, 2018
View Articletitled, Numerical Investigation of Convective Heat Transfer to Supercritical Pressure Hydrogen in a Straight Tube
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Topics: Convection, Heat transfer, Hydrogen, Pressure, Simulation, Turbulence, Flow (Dynamics), Density, Temperature, Viscosity
Journal Articles

Transient Heat Transfer in an Out-of-Pile SCWR Fuel Assembly Test at Near-Critical Pressure

Free
Thomas Schulenberg, Hongbo Li
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2018, 4(1): 011005.
Paper No: NERS-17-1026
https://doi.org/10.1115/1.4038061
Published Online: December 4, 2017
View Articletitled, Transient Heat Transfer in an Out-of-Pile SCWR Fuel Assembly Test at Near-Critical Pressure
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Topics: Heat transfer, Pressure, Supercritical water reactors, Temperature, Transient heat transfer, Fuels, Film boiling, Rods, Heat flux, Transients (Dynamics)
Journal Articles

Research Challenges of Heat Transfer to Supercritical Fluids

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X. Cheng, X. J. Liu
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2018, 4(1): 011003.
Paper No: NERS-17-1024
https://doi.org/10.1115/1.4037117
Published Online: December 4, 2017
View Articletitled, Research Challenges of Heat Transfer to Supercritical Fluids
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Topics: Heat transfer, Supercritical fluids, Temperature, Wall temperature, Water, Numerical analysis, Heat flux, Fluids, Turbulence, Flow (Dynamics)
Journal Articles

Large Eddy Simulation Study on Forced Convection Heat Transfer to Water at Supercritical Pressure in a Trapezoid Annulus

Free
Muhsin Mohd Amin, Yu Duan, Shuisheng He
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2018, 4(1): 011007.
Paper No: NERS-17-1043
https://doi.org/10.1115/1.4038161
Published Online: December 4, 2017
View Articletitled, Large Eddy Simulation Study on Forced Convection Heat Transfer to Water at Supercritical Pressure in a Trapezoid Annulus
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Topics: Flow (Dynamics), Forced convection, Pressure, Temperature, Water, Heat flux, Large eddy simulation, Heating, Annulus, Fluids
Journal Articles

Saturated Pool Nucleate Boiling on Heat Transfer Surface With Deposited Sea Salts

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Shinichiro Uesawa, Yasuo Koizumi, Mitsuhiko Shibata, Hiroyuki Yoshida
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2017, 3(4): 041002.
Paper No: NERS-16-1165
https://doi.org/10.1115/1.4036987
Published Online: July 31, 2017
View Articletitled, Saturated Pool Nucleate Boiling on Heat Transfer Surface With Deposited Sea Salts
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Topics: Boiling, Heat transfer, Seas, Seawater, Temperature, Water, Heat flux, Fluids, Nucleate boiling, Bubbles