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Journal Articles

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

Dong Yang, Jiaxiang Chen, Yongchang Feng, Lin Chen

ASME J of Nuclear Rad Sci. April 2022, 8(2): 021402.

Paper No: NERS-20-1194

DOI: https://doi.org/10.1115/1.4051248

Published Online: October 19, 2021

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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

Zefeng Wang, Jian Deng, Zhifang Qiu, Xiaoyu Wang, Lei Zhong, Mingjun Zhong

ASME J of Nuclear Rad Sci. April 2022, 8(2): 021403.

Paper No: NERS-20-1202

DOI: https://doi.org/10.1115/1.4051875

Published Online: October 19, 2021

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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

Aleksander Grah, Haileyesus Tsige-Tamirat, Joel Guidez, Antoine Gerschenfeld, Konstantin Mikityuk, Janos Bodi, Enrico Girardi

ASME J of Nuclear Rad Sci. January 2022, 8(1): 011314.

Paper No: NERS-20-1204

DOI: https://doi.org/10.1115/1.4051292

Published Online: September 20, 2021

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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

Kapil Bodkha, N. K. Maheshwari

ASME J of Nuclear Rad Sci. July 2021, 7(3): 030802.

Paper No: NERS-20-1029

DOI: https://doi.org/10.1115/1.4048898

Published Online: February 19, 2021

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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

David Rot, Jan Hrbek, Jakub Jirinec

ASME J of Nuclear Rad Sci. April 2021, 7(2): 021602.

Paper No: NERS-20-1147

DOI: https://doi.org/10.1115/1.4048899

Published Online: November 16, 2020

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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

Michal Knedlík, David Rot, Jan Hrbek

ASME J of Nuclear Rad Sci. April 2021, 7(2): 021801.

Paper No: NERS-20-1140

DOI: https://doi.org/10.1115/1.4048632

Published Online: October 30, 2020

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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

Santosh K. Pradhan, K. Obaidurrahman, Kannan N. Iyer

ASME J of Nuclear Rad Sci. January 2021, 7(1): 011502.

Paper No: NERS-19-1155

DOI: https://doi.org/10.1115/1.4046254

Published Online: October 1, 2020

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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

Mahesh Kumar Yadav, Maneesh Punetha, Abhinav Bhanawat, Sameer Khandekar, Pavan K. Sharma

ASME J of Nuclear Rad Sci. October 2020, 6(4): 041108.

Paper No: NERS-19-1164

DOI: https://doi.org/10.1115/1.4046910

Published Online: September 4, 2020

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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

Sai Raja Gopal Vadlamudi, Arun K. Nayak

ASME J of Nuclear Rad Sci. October 2020, 6(4): 041109.

Paper No: NERS-19-1165

DOI: https://doi.org/10.1115/1.4048124

Published Online: September 4, 2020

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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

Angel Papukchiev

ASME J of Nuclear Rad Sci. April 2020, 6(2): 021104.

Paper No: NERS-19-1029

DOI: https://doi.org/10.1115/1.4045074

Published Online: January 29, 2020

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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

Rosario Delgado-Tardáguila, Marisol Corisco, Antonio Espejo, Daniel Navarro, Javier Riverola

ASME J of Nuclear Rad Sci. April 2019, 5(2): 020909.

Paper No: NERS-18-1057

DOI: https://doi.org/10.1115/1.4042358

Published Online: March 15, 2019

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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

Hiroshi Madokoro, Alexei Miassoedov, Thomas Schulenberg

ASME J of Nuclear Rad Sci. January 2019, 5(1): 011017.

Paper No: NERS-18-1035

DOI: https://doi.org/10.1115/1.4041278

Published Online: January 24, 2019

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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

Yu Ji, Jun Sun, Lei Shi

ASME J of Nuclear Rad Sci. July 2018, 4(3): 031012.

Paper No: NERS-17-1193

DOI: https://doi.org/10.1115/1.4039600

Published Online: May 16, 2018

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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

Thomas Schulenberg, Hongbo Li

ASME J of Nuclear Rad Sci. January 2018, 4(1): 011005.

Paper No: NERS-17-1026

DOI: https://doi.org/10.1115/1.4038061

Published Online: December 4, 2017

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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

X. Cheng, X. J. Liu

ASME J of Nuclear Rad Sci. January 2018, 4(1): 011003.

Paper No: NERS-17-1024

DOI: https://doi.org/10.1115/1.4037117

Published Online: December 4, 2017

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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

Muhsin Mohd Amin, Yu Duan, Shuisheng He

ASME J of Nuclear Rad Sci. January 2018, 4(1): 011007.

Paper No: NERS-17-1043

DOI: https://doi.org/10.1115/1.4038161

Published Online: December 4, 2017

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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

Shinichiro Uesawa, Yasuo Koizumi, Mitsuhiko Shibata, Hiroyuki Yoshida

ASME J of Nuclear Rad Sci. October 2017, 3(4): 041002.

Paper No: NERS-16-1165

DOI: https://doi.org/10.1115/1.4036987

Published Online: July 31, 2017

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Topics: Boiling, Heat transfer, Seas, Seawater, Temperature, Water, Heat flux, Fluids, Nucleate boiling, Bubbles

Journal Articles

Influence of Boundary Conditions, Vessel Geometry, and Simulant Materials on the Heat Transfer of Volumetrically Heated Melt in a Light Water Reactor Lower Head

X. Gaus-Liu, A. Miassoedov

ASME J of Nuclear Rad Sci. July 2017, 3(3): 031003.

Paper No: NERS-16-1107

DOI: https://doi.org/10.1115/1.4035853

Published Online: May 25, 2017

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Topics: Boundary-value problems, Cooling, Heat flux, Heat transfer, Temperature, Vessels, Geometry, Insulation, Water

Journal Articles

Results of Air Barbotage Experiments Simulating Two-Phase Flow in a CANDU End Shield During In-Vessel Retention

Justin H. Spencer

ASME J of Nuclear Rad Sci. April 2017, 3(2): 021008.

Paper No: NERS-16-1075

DOI: https://doi.org/10.1115/1.4035566

Published Online: March 1, 2017

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Topics: Boiling, Cavities, Flow visualization, Heat, Heat flux, Vessels, Water, Accidents, Air flow, Porous materials

Journal Articles

A Space–Time-Dependent Study of Control Rods Withdrawal in a Large-Size Pressurized Water Reactor

Sanjeev Kumar, K. Obaidurrahman, Om Pal Singh, Prabhat Munshi

ASME J of Nuclear Rad Sci. January 2017, 3(1): 011015.

Paper No: NERS-16-1007

DOI: https://doi.org/10.1115/1.4034478

Published Online: December 20, 2016

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Topics: Heat flux, Nucleate boiling, Pressurized water reactors, Rods, Safety, Scram, Spacetime, Thermal hydraulics, Transients (Dynamics), Temperature profiles

Journal citation

NARROW

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

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

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

Heat Transfer in Supercritical Fluids: A Review

Heat Transfer in Induction Melting of Aluminum Oxide in Cold Crucible

Manipulation System for Measuring Heat Flux in Radioactive Melt

A Simplified Two-Group Multipoint Kinetics Model

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

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

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

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

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

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

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

Research Challenges of Heat Transfer to Supercritical Fluids

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

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

Influence of Boundary Conditions, Vessel Geometry, and Simulant Materials on the Heat Transfer of Volumetrically Heated Melt in a Light Water Reactor Lower Head

Results of Air Barbotage Experiments Simulating Two-Phase Flow in a CANDU End Shield During In-Vessel Retention

A Space–Time-Dependent Study of Control Rods Withdrawal in a Large-Size Pressurized Water Reactor

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