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Journal Articles

Estimation of Turbulent Mixing Factor and Study of Turbulent Flow Structures in PWR Sub Channel by DNS

Accepted Manuscript
Raj Kumar Singh, Deb Mukhopadhyay, Devang Khakhar, J. B. Joshi
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci.
Paper No: NERS-24-1004
https://doi.org/10.1115/1.4066001
Published Online: July 20, 2024
View Article titled, Estimation of Turbulent Mixing Factor and Study of Turbulent Flow Structures in PWR Sub Channel by DNS
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Topics: Pressurized water reactors, Turbulence, Computational fluid dynamics, Design, Computer simulation, Dynamics (Mechanics), Equilibrium (Physics), Fuels, Geometry, Momentum
Journal Articles

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

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 Article titled, 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

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

Development and Verification of Multiphysical Coupling Calculation Code for Typical Pressured Water Reactor Core

Zhigang Li, Ping An, Junjie Pan, Wei Liu, Wei Lu, Shenglong Qiang
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Technical Briefs
ASME J of Nuclear Rad Sci. July 2021, 7(3): 034504.
Paper No: NERS-20-1038
https://doi.org/10.1115/1.4048027
Published Online: March 16, 2021
View Article titled, Development and Verification of Multiphysical Coupling Calculation Code for Typical Pressured Water Reactor Core
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Topics: Dynamics (Mechanics), Fuels, Neutrons, Pressurized water reactors, Spacetime, Temperature, Transients (Dynamics), Water, Cylinders, Computational methods
Journal Articles

Flow Instability Investigation at Supercritical Pressures in Parallel Channels by Computational Fluid Dynamics Adopting Low- and High-Power Boundaries

Edward Shitsi, Seth Kofi Debrah, Vincent Yao Agbodemegbe, Emmanuel Ampomah-Amoako
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2021, 7(1): 011401.
Paper No: NERS-19-1142
https://doi.org/10.1115/1.4046255
Published Online: October 1, 2020
View Article titled, Flow Instability Investigation at Supercritical Pressures in Parallel Channels by Computational Fluid Dynamics Adopting Low- and High-Power Boundaries
Open the PDF for Flow Instability Investigation at Supercritical Pressures in Parallel Channels by Computational Fluid Dynamics Adopting Low- and High-Power Boundaries in another window
Topics: Computational fluid dynamics, Flow (Dynamics), Flow instability, Gravity (Force), Oscillations, Pressure, Temperature, Heating, Turbulence, Coolants
Journal Articles

Simulation of IAEA Reactivity Initiated Transient Benchmarks Using Reactor Dynamics Code “REDAC”

Vivek A. Kale, Obaidurrahman K.
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2020, 6(3): 031501.
Paper No: NERS-19-1074
https://doi.org/10.1115/1.4045394
Published Online: March 9, 2020
View Article titled, Simulation of IAEA Reactivity Initiated Transient Benchmarks Using Reactor Dynamics Code “REDAC”
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Topics: Coolants, Fuels, Neutrons, Simulation, Temperature, Transients (Dynamics), Dynamics (Mechanics), Thermal hydraulics
Journal Articles

Level Dynamics Monitoring of a Once-Through Steam Generator: A New Method Using the Reflectometric Technique

Francesco Cordella, Mauro Cappelli, Massimo Sepielli
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research Papers
ASME J of Nuclear Rad Sci. October 2016, 2(4): 041003.
Paper No: NERS-15-1181
https://doi.org/10.1115/1.4033696
Published Online: October 12, 2016
View Article titled, Level Dynamics Monitoring of a Once-Through Steam Generator: A New Method Using the Reflectometric Technique
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Topics: Algorithms, Boilers, Dynamics (Mechanics), Pressure, Sensors, Temperature, Transients (Dynamics), Water, Flow (Dynamics), Transmission lines