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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

A Simple Analytical Model to Predict the Freeze Plug Opening Time in Molten Salt Reactors

Muhammad Ilham, Tomio Okawa
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Technical Briefs
ASME J of Nuclear Rad Sci. October 2023, 9(4): 041107.
Paper No: NERS-22-1162
https://doi.org/10.1115/1.4062879
Published Online: July 17, 2023
View Article titled, A Simple Analytical Model to Predict the Freeze Plug Opening Time in Molten Salt Reactors
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Topics: Molten salt reactors, Simulation, Wall thickness, Safety, Computer simulation, Design, Temperature, Heat conduction, Melting, Solidification
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
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Topics: Coolants, Fluids, Fuel rods, Heat transfer, Momentum, Temperature, Water, Wall temperature, Flow (Dynamics), Testing
Journal Articles

Nonhyperbolicity of Conservation Equations of RELAP5 Two-Fluid Model in Nuclear Reactor Safety Results (Investigation and Eigenvalue Analysis)

S. P. Saraswat, P. Munshi, C. Allison
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2021, 7(1): 011402.
Paper No: NERS-19-1022
https://doi.org/10.1115/1.4047161
Published Online: October 2, 2020
View Article titled, Nonhyperbolicity of Conservation Equations of RELAP5 Two-Fluid Model in Nuclear Reactor Safety Results (Investigation and Eigenvalue Analysis)
Open the PDF for Nonhyperbolicity of Conservation Equations of RELAP5 Two-Fluid Model in Nuclear Reactor Safety Results (Investigation and Eigenvalue Analysis) in another window
Topics: Accidents, Boiling water reactors, Eigenvalues, Fluids, Porosity, Pressure, Pressurized water reactors, Light water reactors, Water, Stability
Journal Articles

Validation of Selected Cesar Friction Models of the ASTECV21 Code Based on Moby Dick Experiments

I. Gómez-García-Toraño, L. Laborde
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2019, 5(2): 020908.
Paper No: NERS-18-1070
https://doi.org/10.1115/1.4042119
Published Online: March 15, 2019
View Article titled, Validation of Selected Cesar Friction Models of the ASTECV21 Code Based on Moby Dick Experiments
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Topics: Flow (Dynamics), Friction, Momentum, Pressure, Pressure drop
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
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 Article titled, 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