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Journal Articles

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

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

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 Article titled, 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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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

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 Article titled, 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

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

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

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 Article titled, 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

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 Article titled, 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

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 Article titled, 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

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 Article titled, 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

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 Article titled, 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

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

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

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 Article titled, 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

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 Article titled, 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

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 Article titled, 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

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 Article titled, 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

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

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 Article titled, 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

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 Article titled, 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

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 Article titled, 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

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 Article titled, 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
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