1-20 of 105
Heat
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
Journal Articles

Impact of the abrasive solution heating process with different techniques on the etching parameters for the SSNTD (CN-85)

Accepted Manuscript
Manar Dheyaa Salim, Hyam Nazmy Khalaf, Awsam Abdulsattar Marzaali, Mostafa Mostafa
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci.
Paper No: NERS-24-1052
https://doi.org/10.1115/1.4066805
Published Online: October 11, 2024
View Article titled, Impact of the abrasive solution heating process with different techniques on the etching parameters for the SSNTD (CN-85)
Open the PDF for Impact of the abrasive solution heating process with different techniques on the etching parameters for the SSNTD (CN-85) in another window
Topics: Etching, Heating, Heat, Convection, Heat conduction, Irradiation (Radiation exposure), Sensors, Water, Electromagnetic radiation, Heat transfer
Journal Articles

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

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 Article titled, Heat Flux Correlations for Condensation From Steam and Air Mixtures on Vertical Flat Plates
Open the PDF for Heat Flux Correlations for Condensation From Steam and Air Mixtures on Vertical Flat Plates in another window
Topics: Condensation, Flat plates, Heat, Heat flux, Natural convection
Journal Articles

Implementation of Solar Salt Properties Into ARIANT and Simulation of Pressurized Loss of Forced Circulation in a High Temperature Gas-Cooled Small Modular Reactor

Jason H. Wu, Thomas G. Beuthe, Aleksandar Vasić
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2024, 10(3): 030905.
Paper No: NERS-23-1051
https://doi.org/10.1115/1.4062917
Published Online: March 8, 2024
View Article titled, Implementation of Solar Salt Properties Into ARIANT and Simulation of Pressurized Loss of Forced Circulation in a High Temperature Gas-Cooled Small Modular Reactor
Open the PDF for Implementation of Solar Salt Properties Into ARIANT and Simulation of Pressurized Loss of Forced Circulation in a High Temperature Gas-Cooled Small Modular Reactor in another window
Topics: Heat, Simulation, Solar energy, Temperature, High temperature, Helium, Fuels, Coolants, Fluids, Small modular reactors
Journal Articles

Development and Testing of a System Thermal-Hydraulics Model for a 50-MW el -Class Pressurized Water Reactor–Small Modular Reactor

Shujun Wang, Xianmin Huang, Yanfei Rao, Blair P. Bromley
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2024, 10(2): 021402.
Paper No: NERS-23-1086
https://doi.org/10.1115/1.4063240
Published Online: January 29, 2024
View Article titled, Development and Testing of a System Thermal-Hydraulics Model for a 50-MW el -Class Pressurized Water Reactor–Small Modular Reactor
Open the PDF for Development and Testing of a System Thermal-Hydraulics Model for a 50-MW el -Class Pressurized Water Reactor–Small Modular Reactor in another window
Topics: Boilers, Design, Flow (Dynamics), Pressure, Pressurized water reactors, Small modular reactors, Temperature, Thermal hydraulics, Oscillations, Junctions
Journal Articles

Computational Fluid Dynamics Calculations of Moderator Heat and Fluid Flow of Small Modular Heavy Water Reactor

Tomas Korinek, Radek Skoda, Martin Lovecky, Ondrej Burian
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Technical Briefs
ASME J of Nuclear Rad Sci. January 2024, 10(1): 014501.
Paper No: NERS-23-1015
https://doi.org/10.1115/1.4063007
Published Online: October 20, 2023
View Article titled, Computational Fluid Dynamics Calculations of Moderator Heat and Fluid Flow of Small Modular Heavy Water Reactor
Open the PDF for Computational Fluid Dynamics Calculations of Moderator Heat and Fluid Flow of Small Modular Heavy Water Reactor in another window
Topics: Computational fluid dynamics, Cooling systems, Flow (Dynamics), Fluid dynamics, Heat, Heavy water reactors, Inertia (Mechanics), Pressure, Temperature, Vessels
Journal Articles

System Thermal-Hydraulics Model for Fluoride Salt-Cooled Reactor Based on Small Modular Advanced High Temperature Reactor (SmAHTR) Design Concept

Shujun Wang, Xianmin Huang, Blair P. Bromley
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2023, 9(4): 041302.
Paper No: NERS-23-1011
https://doi.org/10.1115/1.4062500
Published Online: September 15, 2023
View Article titled, System Thermal-Hydraulics Model for Fluoride Salt-Cooled Reactor Based on Small Modular Advanced High Temperature Reactor (SmAHTR) Design Concept
Open the PDF for System Thermal-Hydraulics Model for Fluoride Salt-Cooled Reactor Based on Small Modular Advanced High Temperature Reactor (SmAHTR) Design Concept in another window
Topics: Coolants, Cycles, Design, Flow (Dynamics), Fuels, High temperature, Modeling, Temperature, Thermal hydraulics, Steady state
Journal Articles

Impact of Thermal-Hydraulic Feedback and Differential Thermal Expansion on European Sodium-Cooled Fast Reactor Core Power Distribution

Ben Lindley, Francisco Álvarez Velarde, Una Baker, Janos Bodi, Paul Cosgrove, Alan Charles, Carlo Fiorina, Emil Fridman, Jiri Krepel, Jean Lavarenne, Konstantin Mikityuk, Evgeny Nikitin, Alexander Ponomarev, Stefan Radman, Eugene Shwageraus, Brendan Tollit
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2023, 9(3): 031301.
Paper No: NERS-22-1119
https://doi.org/10.1115/1.4056930
Published Online: March 13, 2023
View Article titled, Impact of Thermal-Hydraulic Feedback and Differential Thermal Expansion on European Sodium-Cooled Fast Reactor Core Power Distribution
Open the PDF for Impact of Thermal-Hydraulic Feedback and Differential Thermal Expansion on European Sodium-Cooled Fast Reactor Core Power Distribution in another window
Topics: Coolants, Density, Feedback, Fuels, Sodium fast reactors, Temperature, Thermal expansion, Manufacturing, Electrical conductance, Heat
Journal Articles

ATHENA Main Heat Exchanger Conceptual Design and Thermal-Hydraulic Assessment With RELAP5 Code

Tommaso Del Moro, Pierdomenico Lorusso, Fabio Giannetti, Mariano Tarantino, Marco Caramello, Daniele Mazzi, Marin Constantin
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2023, 9(4): 041108.
Paper No: NERS-22-1165
https://doi.org/10.1115/1.4056973
Published Online: March 13, 2023
View Article titled, ATHENA Main Heat Exchanger Conceptual Design and Thermal-Hydraulic Assessment With RELAP5 Code
Open the PDF for ATHENA Main Heat Exchanger Conceptual Design and Thermal-Hydraulic Assessment With RELAP5 Code in another window
Topics: Cycles, Heat exchangers, Sensitivity analysis, Water, Fast neutron reactors, Conceptual design, Temperature, Heat, Bathythermographs, Geometry
Journal Articles

Validation of Feedback Reactivity Evaluation Models for Plant Dynamics Analysis Code During Unprotected Loss of Heat Sink Event in Sodium-Cooled Fast Reactors

Kazuo Yoshimura, Norihiro Doda, Kennichi Igawa, Masaaki Tanaka, Hidemasa Yamano
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2023, 9(2): 021601.
Paper No: NERS-21-1160
https://doi.org/10.1115/1.4055328
Published Online: December 14, 2022
View Article titled, Validation of Feedback Reactivity Evaluation Models for Plant Dynamics Analysis Code During Unprotected Loss of Heat Sink Event in Sodium-Cooled Fast Reactors
Open the PDF for Validation of Feedback Reactivity Evaluation Models for Plant Dynamics Analysis Code During Unprotected Loss of Heat Sink Event in Sodium-Cooled Fast Reactors in another window
Topics: Feedback, Sodium fast reactors, Temperature, Fuels, Sensitivity analysis, Density, Heat, Heat sinks, Dynamics (Mechanics), Coolants
Journal Articles

Safety of Radioactive Materials Transportation and Storing Assisted by Internet of Things

M. Zorkany, Hassan F. Morsi
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2022, 8(3): 031901.
Paper No: NERS-20-1010
https://doi.org/10.1115/1.4048113
Published Online: May 27, 2022
View Article titled, Safety of Radioactive Materials Transportation and Storing Assisted by Internet of Things
Open the PDF for Safety of Radioactive Materials Transportation and Storing Assisted by Internet of Things in another window
Topics: Heat, Radioactive substances, Safety, Security, Transportation systems, Internet of things, Embedded systems, Sensors, Vehicles, Radiation (Physics)
Journal Articles

Thermal-Hydraulic Safety Assessment of Full-Scale ESBWR Nuclear Reactor Design

S. P. Saraswat, D. Ray, G. Mishra, D. Yadav, V. S. Bhadouria, P. Munshi, C. Allison
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2022, 8(3): 031403.
Paper No: NERS-21-1073
https://doi.org/10.1115/1.4052014
Published Online: May 26, 2022
View Article titled, Thermal-Hydraulic Safety Assessment of Full-Scale ESBWR Nuclear Reactor Design
Open the PDF for Thermal-Hydraulic Safety Assessment of Full-Scale ESBWR Nuclear Reactor Design in another window
Topics: Accidents, Boiling water reactors, Containment, Design, Pressure, Safety, Steam, Water, Heat, Economics
Journal Articles

Synergy of a Small Modular Reactor for Addressing Remote Communities Non-Nuclear Waste

Glenn Harvel
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2022, 8(3): 031302.
Paper No: NERS-21-1100
https://doi.org/10.1115/1.4052808
Published Online: May 26, 2022
View Article titled, Synergy of a Small Modular Reactor for Addressing Remote Communities Non-Nuclear Waste
Open the PDF for Synergy of a Small Modular Reactor for Addressing Remote Communities Non-Nuclear Waste in another window
Topics: Fuels, Heat, Nuclear power stations, Plastics, Pyrolysis, Small modular reactors, Heating, Syngas, Temperature, Biochar
Journal Articles

Thermal Stratification in a Pool With Submerged Heater Under Low Frequency Excitation

S. P. Chauhan, D. K. Chandraker, Naveen Kumar
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2022, 8(3): 031405.
Paper No: NERS-21-1106
https://doi.org/10.1115/1.4053221
Published Online: May 26, 2022
View Article titled, Thermal Stratification in a Pool With Submerged Heater Under Low Frequency Excitation
Open the PDF for Thermal Stratification in a Pool With Submerged Heater Under Low Frequency Excitation in another window
Topics: Excitation, Thermal stratification, Water, Temperature gradient, Temperature, Heat
Journal Articles

Development and Processing of Thermal-Hydraulic Model for GFR 2400 Fast Reactor Design and NESTLE Coupled Transient Code

Filip Osuský, Branislav Vrban, Štefan Čerba, Jakub Lüley, Vladimír Nečas
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2022, 8(4): 041401.
Paper No: NERS-21-1012
https://doi.org/10.1115/1.4051515
Published Online: March 22, 2022
View Article titled, Development and Processing of Thermal-Hydraulic Model for GFR 2400 Fast Reactor Design and NESTLE Coupled Transient Code
Open the PDF for Development and Processing of Thermal-Hydraulic Model for GFR 2400 Fast Reactor Design and NESTLE Coupled Transient Code in another window
Topics: Coolants, Design, Fast neutron reactors, Fuels, Heat, Temperature, Transients (Dynamics), Temperature distribution, Simulation, Cladding systems (Building)
Journal Articles

Testing the Modified Subchannel tempa-sc Code in Comparison With Experiments and Other Computer Codes

A. M. Baisov, A. N. Churkin, V. I. Deev, V. S. Kharitonov
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2022, 8(3): 031101.
Paper No: NERS-21-1101
https://doi.org/10.1115/1.4053049
Published Online: March 22, 2022
View Article titled, Testing the Modified Subchannel tempa-sc Code in Comparison With Experiments and Other Computer Codes
Open the PDF for Testing the Modified Subchannel tempa-sc Code in Comparison With Experiments and Other Computer Codes in another window
Topics: Coolants, Fluids, Fuel rods, Heat transfer, Momentum, Temperature, Water, Wall temperature, Flow (Dynamics), Testing
Journal Articles

The Effect of Serpent 2 Calculation Parameters on Evaluated Spent Nuclear Fuel Source Term

Riku Tuominen, Ville Valtavirta
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Technical Briefs
ASME J of Nuclear Rad Sci. October 2022, 8(4): 044503.
Paper No: NERS-21-1019
https://doi.org/10.1115/1.4051445
Published Online: March 15, 2022
View Article titled, The Effect of Serpent 2 Calculation Parameters on Evaluated Spent Nuclear Fuel Source Term
Open the PDF for The Effect of Serpent 2 Calculation Parameters on Evaluated Spent Nuclear Fuel Source Term in another window
Topics: Boiling water reactors, Emissions, Heat, Manufacturing, Nuclear fission, Photons, Probability, Resonance, Spent nuclear fuels, Nuclides
Journal Articles

Impact of Approximations in Operating History Data on Spent Fuel Properties With Serpent 2

Silja Häkkinen
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2022, 8(4): 041901.
Paper No: NERS-21-1015
https://doi.org/10.1115/1.4051444
Published Online: March 15, 2022
View Article titled, Impact of Approximations in Operating History Data on Spent Fuel Properties With Serpent 2
Open the PDF for Impact of Approximations in Operating History Data on Spent Fuel Properties With Serpent 2 in another window
Topics: Approximation, Coolants, Cycles, Irradiation (Radiation exposure), Manufacturing, Nuclides, Spent nuclear fuels, Heat, Boron, Photons
Journal Articles

Concept of a Small Modular SCWR With Horizontal Fuel Assemblies

Thomas Schulenberg, Ivan Otic
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Technical Briefs
ASME J of Nuclear Rad Sci. July 2022, 8(3): 031104.
Paper No: NERS-21-1074
https://doi.org/10.1115/1.4052191
Published Online: March 15, 2022
View Article titled, Concept of a Small Modular SCWR With Horizontal Fuel Assemblies
Open the PDF for Concept of a Small Modular SCWR With Horizontal Fuel Assemblies in another window
Topics: Coolants, Design, Fuels, Heat, Supercritical water reactors, Water, Temperature, Light water reactors, Cladding systems (Building), Natural convection
Journal Articles

On Some Differences of the Thermoelectrical Effects in BN-600 and Superphenix

Serguei Podobed
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Technical Briefs
ASME J of Nuclear Rad Sci. April 2022, 8(2): 024505.
Paper No: NERS-20-1167
https://doi.org/10.1115/1.4052591
Published Online: January 11, 2022
View Article titled, On Some Differences of the Thermoelectrical Effects in BN-600 and Superphenix
Open the PDF for On Some Differences of the Thermoelectrical Effects in BN-600 and Superphenix in another window
Topics: Coolants, Currents, Design, Excitation, Liquid metals, Magnetic fields, Pressure, Sodium, Heat exchangers, Pumps
Journal Articles

Guest Editorial by Gilles Rodriguez

Gilles Rodriguez
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Guest Editorial
ASME J of Nuclear Rad Sci. January 2022, 8(1): 010303.
Paper No: NERS-21-1137
https://doi.org/10.1115/1.4052719
Published Online: December 14, 2021
View Article titled, Guest Editorial by Gilles Rodriguez
Open the PDF for Guest Editorial by Gilles Rodriguez in another window
Topics: Carbon, Collaboration, Economics , Energy consumption, Heat, Hydrogen, Industrial capacity, Innovation, Manufacturing systems, Molten salt reactors