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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
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Topics: Condensation, Flat plates, Heat, Heat flux, Natural convection
Journal Articles

Introducing Passive Nuclear Safety in Water-Cooled Reactors: Numerical Simulation and Validation of Natural Convection Heat Transfer and Transport in Packed Beds of Heated Microspheres

Olugbenga O. Noah, Johan F. Slabber, Josua P. Meyer
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2023, 9(3): 031403.
Paper No: NERS-22-1020
https://doi.org/10.1115/1.4056239
Published Online: February 8, 2023
View Article titled, Introducing Passive Nuclear Safety in Water-Cooled Reactors: Numerical Simulation and Validation of Natural Convection Heat Transfer and Transport in Packed Beds of Heated Microspheres
Open the PDF for Introducing Passive Nuclear Safety in Water-Cooled Reactors: Numerical Simulation and Validation of Natural Convection Heat Transfer and Transport in Packed Beds of Heated Microspheres in another window
Topics: Fluids, Heat transfer, Particulate matter, Simulation, Temperature, Flow (Dynamics), Design, Fuels, Safety, Natural convection
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
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Topics: Coolants, Design, Fuels, Heat, Supercritical water reactors, Water, Temperature, Light water reactors, Cladding systems (Building), Natural convection
Journal Articles

Reassessment of Computational Tools for the Modeling of Heat Transfer in a Molten UO 2 Pool in Natural Convection

Claude Jamond, Elena Martin Lopez, Xue-Nong Chen, Nathalie Girault, Pierre Gubernatis, Andrei Rineiski
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2022, 8(1): 011325.
Paper No: NERS-20-1142
https://doi.org/10.1115/1.4052489
Published Online: December 14, 2021
View Article titled, Reassessment of Computational Tools for the Modeling of Heat Transfer in a Molten UO 2 Pool in Natural Convection
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Topics: Fuels, Heat transfer, Modeling, Natural convection, Heat, Temperature, Flux (Metallurgy)
Journal Articles

New Reactor Safety Measures for the European Sodium Fast Reactor—Part I: Conceptual Design

Joel Guidez, Janos Bodi, Konstantin Mikityuk, Enrico Girardi, Bernard Carluec
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2022, 8(1): 011311.
Paper No: NERS-20-1059
https://doi.org/10.1115/1.4051364
Published Online: August 12, 2021
View Article titled, New Reactor Safety Measures for the European Sodium Fast Reactor—Part I: Conceptual Design
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Topics: Heat, Safety, Sodium, Vessels, Pumps, Design, Natural convection, Roofs, Leakage, Water
Journal Articles

New Reactor Safety Measures for the European Sodium Fast Reactor—Part II: Preliminary Assessment

Joel Guidez, Janos Bodi, Konstantin Mikityuk, Enrico Girardi, Jeremy Bittan, Aleksander Grah, Haileyesus Tsige-Tamirat, Pablo Romojaro, Francisco Álvarez-Velarde, Bernard Carluec
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2022, 8(1): 011312.
Paper No: NERS-20-1080
https://doi.org/10.1115/1.4051723
Published Online: August 12, 2021
View Article titled, New Reactor Safety Measures for the European Sodium Fast Reactor—Part II: Preliminary Assessment
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Topics: Cooling systems, Design, Heat, Heat transfer, Pumps, Safety, Sodium, Sodium fast reactors, Temperature, Vessels
Journal Articles

Laminar Natural Convection Heat Transfer From Vertical 7 × 7 Rod Bundles in Liquid Sodium

Koichi Hata, Katsuya Fukuda, Tohru Mizuuchi
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2019, 5(2): 021002.
Paper No: NERS-17-1088
https://doi.org/10.1115/1.4042356
Published Online: March 15, 2019
View Article titled, Laminar Natural Convection Heat Transfer From Vertical 7 × 7 Rod Bundles in Liquid Sodium
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Topics: Cylinders, Fuel rods, Heat transfer, Natural convection, Sodium, Temperature
Journal Articles

Experimental and Numerical Analysis of Mixing Process of Two Component Gases in a Vertical Fluid Layer in a VHTR

Tetsuaki Takeda
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2019, 5(2): 021003.
Paper No: NERS-17-1288
https://doi.org/10.1115/1.4041690
Published Online: March 15, 2019
View Article titled, Experimental and Numerical Analysis of Mixing Process of Two Component Gases in a Vertical Fluid Layer in a VHTR
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Topics: Gases, High temperature, Natural convection, Numerical analysis, Temperature, Diffusion (Physics), Flow (Dynamics), Very high temperature reactors, Low temperature, Fluids
Journal Articles

Experimental Study on Melt Coolability Capability of Calandria Vault Water During Severe Accident in Indian PHWRs for Prolonged Duration

Sumit V. Prasad, A. K. Nayak
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2018, 4(3): 031014.
Paper No: NERS-17-1062
https://doi.org/10.1115/1.4039636
Published Online: May 16, 2018
View Article titled, Experimental Study on Melt Coolability Capability of Calandria Vault Water During Severe Accident in Indian PHWRs for Prolonged Duration
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Topics: Accidents, Boiling, Heat transfer, Heat transfer coefficients, Heavy water reactors, Temperature, Vessels, Water, Heat, Natural convection