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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

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
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2022, 8(2): 021403.
Paper No: NERS-20-1202
https://doi.org/10.1115/1.4051875
Published Online: October 19, 2021
View Article titled, Experimental Investigation of the Transient Pool Boiling Heat Transfer on the Quenching of Vertical Rodlet in Water
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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

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

Suite for Smooth Particle Hydrodynamic Code Relevant to Spherical Plasma Liner Formation and Implosion

Kevin Schillo, Jason Cassibry, Mitchell Rodriguez, Seth Thompson
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2019, 5(4): 042201.
Paper No: NERS-18-1025
https://doi.org/10.1115/1.4042710
Published Online: July 19, 2019
View Article titled, Suite for Smooth Particle Hydrodynamic Code Relevant to Spherical Plasma Liner Formation and Implosion
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Topics: Heat conduction, Particulate matter, Plasmas (Ionized gases), Pressure, Radiation (Physics), Shock (Mechanics), Simulation, Temperature, Viscosity, Vortices
Journal Articles

Method and Validation for Measurement of Effective Thermal Diffusivity and Conductivity of Pebble Bed in High Temperature Gas-Cooled Reactors

Yongyong Wu, Cheng Ren, Rui Li, Xingtuan Yang, Jiyuan Tu, Shengyao Jiang
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2018, 4(3): 031006.
Paper No: NERS-17-1109
https://doi.org/10.1115/1.4039035
Published Online: May 16, 2018
View Article titled, Method and Validation for Measurement of Effective Thermal Diffusivity and Conductivity of Pebble Bed in High Temperature Gas-Cooled Reactors
Open the PDF for Method and Validation for Measurement of Effective Thermal Diffusivity and Conductivity of Pebble Bed in High Temperature Gas-Cooled Reactors in another window
Topics: Errors, Temperature, Thermal conductivity, Thermal diffusivity, Very high temperature reactors, Low temperature, Safety, Heat conduction, Algorithms, Electrical conductivity
Journal Articles

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

Thomas Schulenberg, Hongbo Li
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2018, 4(1): 011005.
Paper No: NERS-17-1026
https://doi.org/10.1115/1.4038061
Published Online: December 4, 2017
View Article titled, Transient Heat Transfer in an Out-of-Pile SCWR Fuel Assembly Test at Near-Critical Pressure
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Topics: Heat transfer, Pressure, Supercritical water reactors, Temperature, Transient heat transfer, Fuels, Film boiling, Rods, Heat flux, Transients (Dynamics)