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Journal Articles

Studies of the Thermalhydraulics Subchannel Code ASSERT-PV 3.2-SC for Supercritical Applications

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Armando Nava-Dominguez, Xianmin Huang, Songyu Liu
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2025, 11(2): 021402.
Paper No: NERS-24-1028
https://doi.org/10.1115/1.4066523
Published Online: November 4, 2024
View Articletitled, Studies of the Thermalhydraulics Subchannel Code ASSERT-PV 3.2-SC for Supercritical Applications
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Topics: Flow (Dynamics), Fluids, Fuels, Heat transfer, Manufacturing, Pressure, Supercritical water reactors, Wall temperature, Water, Wire
Journal Articles

Neutronic Analysis and Fuel Cycle Parameters of Transuranic-UO 2 Fueled Dual Cooled VVER-1000 Assembly

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Md. Tanvir Ahmed, Afroza Shelley, Md. Nobir Hosen
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2024, 10(2): 021602.
Paper No: NERS-23-1069
https://doi.org/10.1115/1.4063757
Published Online: January 29, 2024
View Articletitled, Neutronic Analysis and Fuel Cycle Parameters of Transuranic-UO 2 Fueled Dual Cooled VVER-1000 Assembly
Open the PDF for Neutronic Analysis and Fuel Cycle Parameters of Transuranic-UO 2 Fueled Dual Cooled VVER-1000 Assembly in another window
Topics: Cycles, Fuel rods, Fuels, Manufacturing, Neutron flux, Neutrons, Nuclear fission, Nuclear fuel cycle, Rods, Safety
Journal Articles

Investigation on Applicability of Subchannel Analysis Code ASFRE to Thermal Hydraulics Analysis in Fuel Assembly With Inner Duct Structure of Sodium Cooled Fast Reactor

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Norihiro Kikuchi, Yasutomo Imai, Ryuji Yoshikawa, Norihiro Doda, Masaaki Tanaka
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2023, 9(3): 031401.
Paper No: NERS-21-1158
https://doi.org/10.1115/1.4056463
Published Online: February 8, 2023
View Articletitled, Investigation on Applicability of Subchannel Analysis Code ASFRE to Thermal Hydraulics Analysis in Fuel Assembly With Inner Duct Structure of Sodium Cooled Fast Reactor
Open the PDF for Investigation on Applicability of Subchannel Analysis Code ASFRE to Thermal Hydraulics Analysis in Fuel Assembly With Inner Duct Structure of Sodium Cooled Fast Reactor in another window
Topics: Ducts, Flow (Dynamics), Fuels, Manufacturing, Sodium fast reactors, Temperature, Temperature distribution, Thermal hydraulics, Wire, Fuel rods
Journal Articles

Flow and Heat Transfer Simulation in a Complete Pressurized Water Reactor Fuel Assembly Using Wall-Modeled RANS

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B. Mikuž, F. Roelofs
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2022, 8(4): 041402.
Paper No: NERS-21-1021
https://doi.org/10.1115/1.4051446
Published Online: March 22, 2022
View Articletitled, Flow and Heat Transfer Simulation in a Complete Pressurized Water Reactor Fuel Assembly Using Wall-Modeled RANS
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Topics: Flow (Dynamics), Fuel rods, Fuels, Manufacturing, Pressure drop, Pressurized water reactors, Temperature, Simulation, Reynolds-averaged Navier–Stokes equations, Turbulence
Journal Articles

Testing the Modified Subchannel tempa-sc Code in Comparison With Experiments and Other Computer Codes

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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 Articletitled, 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

Rewetting Analysis of a Pressurized Water Reactor Fuel Slab Using Improved Lumped Models

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Gustavo D. Pereira, Jian Su
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2021, 7(4): 041604.
Paper No: NERS-20-1104
https://doi.org/10.1115/1.4049196
Published Online: August 20, 2021
View Articletitled, Rewetting Analysis of a Pressurized Water Reactor Fuel Slab Using Improved Lumped Models
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Topics: Fuels, Heat, Slabs, Temperature, Temperature profiles, Pressurized water reactors, Systems analysis, Fuel rods
Journal Articles

Further Details of a Numerical Analysis on the Thermal Hydraulic Effect of Wrapped Wire Spacers in Fuel Bundle

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Attila Kiss, Bence Mervay
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2020, 6(3): 031107.
Paper No: NERS-19-1069
https://doi.org/10.1115/1.4046842
Published Online: June 5, 2020
View Articletitled, Further Details of a Numerical Analysis on the Thermal Hydraulic Effect of Wrapped Wire Spacers in Fuel Bundle
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Topics: Flow (Dynamics), Fuel rods, Geometry, Wire, Wall temperature, Fuels, Corners (Structural elements), Temperature
Journal Articles

About the Thermal Hydraulic Analysis Part of a Coupled Study on a Thorium-Fueled SCWR Concept

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Attila Kiss, Béla Hegyesi, Patrik Richárd Ujváry, András Szabolcs Ványi, Gyula Csom
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2020, 6(3): 031108.
Paper No: NERS-19-1070
https://doi.org/10.1115/1.4046904
Published Online: June 5, 2020
View Articletitled, About the Thermal Hydraulic Analysis Part of a Coupled Study on a Thorium-Fueled SCWR Concept
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Topics: Computational fluid dynamics, Flow (Dynamics), Fluids, Fuels, Manufacturing, Supercritical water reactors, Temperature, Fuel rods, Boundary-value problems, Wire
Journal Articles

A Numerical Study of Turbulent Upward Flow of Super Critical Water in a 2 × 2 Rod Bundle With Nonuniform Heating

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Bo Liu, Shuisheng He, Charles Moulinec, Juan Uribe
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2020, 6(3): 031111.
Paper No: NERS-19-1080
https://doi.org/10.1115/1.4046260
Published Online: June 5, 2020
View Articletitled, A Numerical Study of Turbulent Upward Flow of Super Critical Water in a 2 × 2 Rod Bundle With Nonuniform Heating
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Topics: Flow (Dynamics), Fuel rods, Turbulence, Water, Buoyancy, Heating, Simulation, Temperature, Heat transfer, Computational fluid dynamics
Journal Articles

Evaluation of Radiation Effects on Residents Living Around the NSRR Under External Hazards

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Yuiko Motome, Yoshiya Akiyama, Hiroyuki Murao
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2020, 6(2): 021115.
Paper No: NERS-19-1073
https://doi.org/10.1115/1.4045075
Published Online: February 3, 2020
View Articletitled, Evaluation of Radiation Effects on Residents Living Around the NSRR Under External Hazards
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Topics: Earthquakes, Fuel rods, Fuel storage, Fuels, Radiation (Physics), Safety, Spent fuel storage, Tsunamis, Nuclear fission, Shapes
Journal Articles

Enhanced Accident Tolerance of Thoria-Based Nuclear Fuels

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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 Articletitled, 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

Computational Fluid Dynamics Simulation of Flow-Mixing and Heat Transfer in 4 × 4 Rod Bundle With a Twist-Vane Spacer Grid

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Ganesh Lal Kumawat, Anuj Kumar Kansal, Naresh Kumar Maheshwari, Avaneesh Sharma
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2019, 5(4): 041301.
Paper No: NERS-18-1042
https://doi.org/10.1115/1.4042120
Published Online: July 19, 2019
View Articletitled, Computational Fluid Dynamics Simulation of Flow-Mixing and Heat Transfer in 4 × 4 Rod Bundle With a Twist-Vane Spacer Grid
Open the PDF for Computational Fluid Dynamics Simulation of Flow-Mixing and Heat Transfer in 4 × 4 Rod Bundle With a Twist-Vane Spacer Grid in another window
Topics: Computational fluid dynamics, Flow (Dynamics), Fuel rods, Heat transfer, Simulation, Turbulence
Journal Articles

Rod Bow Ultrasonic Measurements Possibilities

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Marcin Kopeć, Martina Malá
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2019, 5(3): 030901.
Paper No: NERS-18-1044
https://doi.org/10.1115/1.4041277
Published Online: April 16, 2019
View Articletitled, Rod Bow Ultrasonic Measurements Possibilities
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Topics: Fuel rods, Probes, Inspection, Ultrasonic measurement, Fuels, Radiation (Physics), Nuclear fuels
Journal Articles

Simulation of Nuclear Fuel Behavior in Accident Conditions With the DIONISIO Code

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Martín Lemes, Alicia Denis, Alejandro Soba
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2019, 5(2): 020903.
Paper No: NERS-18-1078
https://doi.org/10.1115/1.4042705
Published Online: March 15, 2019
View Articletitled, Simulation of Nuclear Fuel Behavior in Accident Conditions With the DIONISIO Code
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Topics: Accidents, Cladding systems (Building), Coolants, Fuel rods, Fuels, High temperature, Hydrogen, Simulation, Temperature, Water
Journal Articles

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

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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 Articletitled, 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

Implementation of Hydrogen Solid Solubility Data and Precipitation Threshold Stresses in the Fuel Rod Code TESPA-ROD

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Felix Boldt
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2019, 5(2): 020904.
Paper No: NERS-18-1065
https://doi.org/10.1115/1.4042118
Published Online: March 15, 2019
View Articletitled, Implementation of Hydrogen Solid Solubility Data and Precipitation Threshold Stresses in the Fuel Rod Code TESPA-ROD
Open the PDF for Implementation of Hydrogen Solid Solubility Data and Precipitation Threshold Stresses in the Fuel Rod Code TESPA-ROD in another window
Topics: Cladding systems (Building), Fuel rods, Heat, Hydrogen, Precipitation, Storage, Stress, Temperature, Transients (Dynamics), Simulation
Journal Articles

Discussion of Tag Gas Method Using in China Experimental Fast Reactor for Failed Fuel Assembly Location

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Bie Yewang, Zhang Donghui, Xiong Wenbin, Li Huwei, Wu Mingyu, Wang Xinzhe
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2018, 4(4): 041018.
Paper No: NERS-17-1272
https://doi.org/10.1115/1.4040029
Published Online: September 10, 2018
View Articletitled, Discussion of Tag Gas Method Using in China Experimental Fast Reactor for Failed Fuel Assembly Location
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Topics: China, Fast neutron reactors, Fuels, Manufacturing, Fuel rods, Isotopes, Heat transfer, Failure, Cladding systems (Building), Design
Journal Articles

Multiphysics Modeling of Pressurized Water Reactor Fuel Performance

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Wang Zhu, Zhang Chungyu, Yuan Cenxi
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2018, 4(3): 031008.
Paper No: NERS-17-1103
https://doi.org/10.1115/1.4039848
Published Online: May 16, 2018
View Articletitled, Multiphysics Modeling of Pressurized Water Reactor Fuel Performance
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Topics: Cladding systems (Building), Fuel rods, Fuels, Modeling, Nuclear fission, Temperature, Pressurized water reactors, Stress, Accidents
Journal Articles

Assessment of Convective Heat Transfer Correlations Against an Expanded Database for Different Fluids at Supercritical Pressures

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Hussam A. M. Zahlan, Laurence K. H. Leung, Yan-Ping Huang, Guang-Xu Liu
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2018, 4(1): 011004.
Paper No: NERS-17-1050
https://doi.org/10.1115/1.4037720
Published Online: December 4, 2017
View Articletitled, Assessment of Convective Heat Transfer Correlations Against an Expanded Database for Different Fluids at Supercritical Pressures
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Topics: Carbon dioxide, Databases, Flow (Dynamics), Fluids, Fuel rods, Water, Heat transfer, Uncertainty, Annulus
Journal Articles

Computational Fluid Dynamic Simulations of Heat Transfer From a 2 × 2 Wire-Wrapped Fuel Rod Bundle to Supercritical Pressure Water

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Krishna Podila, Yanfei Rao
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2018, 4(1): 011008.
Paper No: NERS-17-1027
https://doi.org/10.1115/1.4037747
Published Online: December 4, 2017
View Articletitled, Computational Fluid Dynamic Simulations of Heat Transfer From a 2 × 2 Wire-Wrapped Fuel Rod Bundle to Supercritical Pressure Water
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Topics: Computational fluid dynamics, Flow (Dynamics), Fuel rods, Heat transfer, Pressure, Simulation, Turbulence, Water, Wire, Temperature