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Journal Articles

Effect of Niobium on Sintering Process of Gamma Phase Uranium Alloys Fuel Pellets

Keke Hou, Chao Yan, Peng Wang, Changqing Cao, Jun Lin, Yanguang Cui, Junqiang Lu, Libing Zhu
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2023, 9(4): 041101.
Paper No: NERS-22-1130
https://doi.org/10.1115/1.4062795
Published Online: July 17, 2023
View Article titled, Effect of Niobium on Sintering Process of Gamma Phase Uranium Alloys Fuel Pellets
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Topics: Alloys, Fuels, Sintering, Uranium, Thermal conductivity, Density
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

Thermophysical Characteristics of Liquid Metal In-Bi-Sn Eutectic (Field's Metal) as a Similarity Coolant

Adam Lipchitz, Glenn Harvel, T. Sunagawa
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2022, 8(3): 031301.
Paper No: NERS-21-1079
https://doi.org/10.1115/1.4053632
Published Online: May 26, 2022
View Article titled, Thermophysical Characteristics of Liquid Metal In-Bi-Sn Eutectic (Field's Metal) as a Similarity Coolant
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Topics: Density, Liquid metals, Metals, Temperature, Thermal conductivity, Viscosity, Specific heat, Alloys
Journal Articles

An Experimental and Numerical Study of Wall Effect on Freeze Valve Performance in a Molten Salt Reactor

Indarta Kuncoro Aji, Tokushima Tatsuya, Motoyasu Kinoshita, Tomio Okawa
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2020, 6(2): 021105.
Paper No: NERS-19-1051
https://doi.org/10.1115/1.4045180
Published Online: January 29, 2020
View Article titled, An Experimental and Numerical Study of Wall Effect on Freeze Valve Performance in a Molten Salt Reactor
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Topics: Cylinders, Molten salt reactors, Temperature, Valves, Brass (Metal), Thermal conductivity, Melting, Computer simulation, Copper, Fuels
Journal Articles

Enhanced Accident Tolerance of Thoria-Based Nuclear Fuels

B. Szpunar, J. A. Szpunar
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2020, 6(1): 011108.
Paper No: NERS-19-1046
https://doi.org/10.1115/1.4044751
Published Online: November 8, 2019
View Article titled, Enhanced Accident Tolerance of Thoria-Based Nuclear Fuels
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Topics: Accidents, Atoms, Diffusion (Physics), Fuel rods, Fuels, Helium, Nuclear fuels, Oxygen, Temperature, Temperature gradient
Journal Articles

Sensitivity Analysis of Unsteady Corium Solidification in an Initially Emptied Horizontal Turbulent Pipe Flow

Shawn Somers-Neal, Vien Nguyen, Edgar Matida, Vinh Tang, Tarik Kaya
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2020, 6(1): 011110.
Paper No: NERS-19-1050
https://doi.org/10.1115/1.4044747
Published Online: November 8, 2019
View Article titled, Sensitivity Analysis of Unsteady Corium Solidification in an Initially Emptied Horizontal Turbulent Pipe Flow
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Topics: Pipes, Reynolds number, Solidification, Temperature, Turbulence, Thermal conductivity, Flow (Dynamics), Simulation, Pipe flow, Freezing
Journal Articles

A Thoria and Thorium Uranium Dioxide Nuclear Fuel Performance Model Prototype and Knowledge Gap Assessment

J. S. Bell, P. K. Chan, A. Prudil
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2019, 5(1): 011005.
Paper No: NERS-17-1064
https://doi.org/10.1115/1.4039778
Published Online: January 24, 2019
View Article titled, A Thoria and Thorium Uranium Dioxide Nuclear Fuel Performance Model Prototype and Knowledge Gap Assessment
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Topics: Fuels, Temperature, Uranium, Irradiation (Radiation exposure), Deformation, Thermal conductivity, Modeling, Nuclear fission
Journal Articles

Numerical Investigation of Convective Heat Transfer to Supercritical Pressure Hydrogen in a Straight Tube

Yu Ji, Jun Sun, Lei Shi
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2018, 4(3): 031012.
Paper No: NERS-17-1193
https://doi.org/10.1115/1.4039600
Published Online: May 16, 2018
View Article titled, Numerical Investigation of Convective Heat Transfer to Supercritical Pressure Hydrogen in a Straight Tube
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Topics: Convection, Heat transfer, Hydrogen, Pressure, Simulation, Turbulence, Flow (Dynamics), Density, Temperature, Viscosity
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
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Topics: Errors, Temperature, Thermal conductivity, Thermal diffusivity, Very high temperature reactors, Low temperature, Safety, Heat conduction, Algorithms, Electrical conductivity
Journal Articles

Study on Radial Temperature Distribution of Aluminum Dispersed Nuclear Fuels: U 3 O 8 -Al, U 3 Si 2 -Al, and UN-Al

Jayangani I. Ranasinghe, Ericmoore Jossou, Linu Malakkal, Barbara Szpunar, Jerzy A. Szpunar
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2018, 4(3): 031020.
Paper No: NERS-17-1304
https://doi.org/10.1115/1.4039886
Published Online: May 16, 2018
View Article titled, Study on Radial Temperature Distribution of Aluminum Dispersed Nuclear Fuels: U 3 O 8 -Al, U 3 Si 2 -Al, and UN-Al
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Topics: Fuels, Nuclear fuels, Thermal conductivity, Temperature, Temperature gradient, Temperature profiles
Journal Articles

Numerical Simulation Research on the Performance of SCWR Fuel Rod

Changbing Tang, Shuo Xing, Hua Pang, Ping Chen, Yi Zhou
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2018, 4(1): 011014.
Paper No: NERS-17-1029
https://doi.org/10.1115/1.4038060
Published Online: December 4, 2017
View Article titled, Numerical Simulation Research on the Performance of SCWR Fuel Rod
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Topics: Cladding systems (Building), Computer simulation, Fuel rods, Fuels, Irradiation (Radiation exposure), Stainless steel, Supercritical water reactors, Temperature, Thermal expansion, Thermal conductivity
Journal Articles

An Finite Element Method Study of the Thermal Conductivity of Polycrystalline UO 2

Enze Jin, Chen Liu, Heming He
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2017, 3(4): 041006.
Paper No: NERS-16-1099
https://doi.org/10.1115/1.4037189
Published Online: July 31, 2017
View Article titled, An Finite Element Method Study of the Thermal Conductivity of Polycrystalline UO 2
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Topics: Grain size, Thermal conductivity, Porosity, Entropy, Finite element methods
Journal Articles

Thermal Predictions of the AGR-3/4 Experiment With Time-Varying Gas Gaps

Grant L. Hawkes, James W. Sterbentz, John T. Maki
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research Papers
ASME J of Nuclear Rad Sci. October 2015, 1(4): 041012.
Paper No: NERS-15-1006
https://doi.org/10.1115/1.4030046
Published Online: September 3, 2015
View Article titled, Thermal Predictions of the AGR-3/4 Experiment With Time-Varying Gas Gaps
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Topics: Fluence (Radiation measurement), Fuels, Graphite, Neutrons, Temperature, Thermal conductivity, Heat, Irradiation (Radiation exposure)
Journal Articles

Computational Fluid Dynamics Analysis for Asymmetric Power Generation in a Prismatic Fuel Block of Fluoride-Salt-Cooled High-Temperature Test Reactor

Wen-Chi Cheng, Kaichao Sun, Lin-Wen Hu, Ching-Chang Chieng
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research Papers
ASME J of Nuclear Rad Sci. January 2015, 1(1): 011003.
Paper No: NERS-14-1009
https://doi.org/10.1115/1.4026391
Published Online: February 9, 2015
View Article titled, Computational Fluid Dynamics Analysis for Asymmetric Power Generation in a Prismatic Fuel Block of Fluoride-Salt-Cooled High-Temperature Test Reactor
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Topics: Computational fluid dynamics, Coolants, Energy generation, Fuels, Graphite, Heat flux, Laminar flow, Temperature, Turbulence, Wall temperature