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Journal Articles

An Improved Heat Flux Partitioning Model of Nucleate Boiling Under Saturated Pool Boiling Condition

Mingfu He, Minghui Chen
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2024, 10(3): 031401.
Paper No: NERS-23-1093
https://doi.org/10.1115/1.4064337
Published Online: April 17, 2024
View Article titled, An Improved Heat Flux Partitioning Model of Nucleate Boiling Under Saturated Pool Boiling Condition
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Topics: Bubbles, Dynamics (Mechanics), Heat flux, Heat transfer, Nucleate boiling, Pool boiling, Boiling, Nucleation (Physics), Quenching (Metalworking), Critical heat flux
Journal Articles

Mechanical Properties of Irradiated U-10 wt. %Mo Alloy Degraded by Porosity Development

Jason L. Schulthess, Katelyn Baird, Philip Petersen, Daniele Salvato, Hakan Ozaltun, William A. Hanson, Nicholas Ullum, Jeffrey Giglio, James I. Cole
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2024, 10(3): 031601.
Paper No: NERS-23-1114
https://doi.org/10.1115/1.4064779
Published Online: April 17, 2024
View Article titled, Mechanical Properties of Irradiated U-10 wt. %Mo Alloy Degraded by Porosity Development
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Topics: Bending strength, Density, Fuels, Mechanical properties, Nuclear fission, Porosity, Stress, Young's modulus, Zirconium, Alloys
Journal Articles

On Frequency/Time Invariance of Certain Temporal and Complex Transfer Functions for the One-Dimensional Interfacial Monochromatic Neutron Density Wave

Nassar H. S. Haidar
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2024, 10(2): 021501.
Paper No: NERS-23-1061
https://doi.org/10.1115/1.4063291
Published Online: October 20, 2023
View Article titled, On Frequency/Time Invariance of Certain Temporal and Complex Transfer Functions for the One-Dimensional Interfacial Monochromatic Neutron Density Wave
Open the PDF for On Frequency/Time Invariance of Certain Temporal and Complex Transfer Functions for the One-Dimensional Interfacial Monochromatic Neutron Density Wave in another window
Topics: Density, Neutrons, Transfer functions, Waves
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

Impact of Thermal-Hydraulic Feedback and Differential Thermal Expansion on European Sodium-Cooled Fast Reactor Core Power Distribution

Ben Lindley, Francisco Álvarez Velarde, Una Baker, Janos Bodi, Paul Cosgrove, Alan Charles, Carlo Fiorina, Emil Fridman, Jiri Krepel, Jean Lavarenne, Konstantin Mikityuk, Evgeny Nikitin, Alexander Ponomarev, Stefan Radman, Eugene Shwageraus, Brendan Tollit
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2023, 9(3): 031301.
Paper No: NERS-22-1119
https://doi.org/10.1115/1.4056930
Published Online: March 13, 2023
View Article titled, Impact of Thermal-Hydraulic Feedback and Differential Thermal Expansion on European Sodium-Cooled Fast Reactor Core Power Distribution
Open the PDF for Impact of Thermal-Hydraulic Feedback and Differential Thermal Expansion on European Sodium-Cooled Fast Reactor Core Power Distribution in another window
Topics: Coolants, Density, Feedback, Fuels, Sodium fast reactors, Temperature, Thermal expansion, Manufacturing, Electrical conductance, Heat
Journal Articles

A Novel Algorithm for Fast Measurement of Material Density in Symmetrical Objects Using X-Ray Radiography

Vaibhav Sinha, Frank Angelo Strantz, Hyoung Koo Lee
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2023, 9(3): 032005.
Paper No: NERS-22-1027
https://doi.org/10.1115/1.4056972
Published Online: March 13, 2023
View Article titled, A Novel Algorithm for Fast Measurement of Material Density in Symmetrical Objects Using X-Ray Radiography
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Topics: Algorithms, Density, Photons, X-rays, Errors
Journal Articles

Validation of Feedback Reactivity Evaluation Models for Plant Dynamics Analysis Code During Unprotected Loss of Heat Sink Event in Sodium-Cooled Fast Reactors

Kazuo Yoshimura, Norihiro Doda, Kennichi Igawa, Masaaki Tanaka, Hidemasa Yamano
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2023, 9(2): 021601.
Paper No: NERS-21-1160
https://doi.org/10.1115/1.4055328
Published Online: December 14, 2022
View Article titled, Validation of Feedback Reactivity Evaluation Models for Plant Dynamics Analysis Code During Unprotected Loss of Heat Sink Event in Sodium-Cooled Fast Reactors
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Topics: Feedback, Sodium fast reactors, Temperature, Fuels, Sensitivity analysis, Density, Heat, Heat sinks, Dynamics (Mechanics), Coolants
Journal Articles

Calculation of Gamma and Neutron Shielding Parameters for Reinforced Polymer Composites

A. M. Osman
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2023, 9(1): 012002.
Paper No: NERS-21-1171
https://doi.org/10.1115/1.4054547
Published Online: June 7, 2022
View Article titled, Calculation of Gamma and Neutron Shielding Parameters for Reinforced Polymer Composites
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Topics: Composite materials, Density, Neutrons, Polymer composites, Relaxation (Physics), Photons, Cross section (Physics), Aluminum, Boron
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

Impact of Approximations in Operating History Data on Spent Fuel Properties With Serpent 2

Silja Häkkinen
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2022, 8(4): 041901.
Paper No: NERS-21-1015
https://doi.org/10.1115/1.4051444
Published Online: March 15, 2022
View Article titled, Impact of Approximations in Operating History Data on Spent Fuel Properties With Serpent 2
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Topics: Approximation, Coolants, Cycles, Irradiation (Radiation exposure), Manufacturing, Nuclides, Spent nuclear fuels, Heat, Boron, Photons
Journal Articles

Build Up and Characterization of Ultraslow Nuclear Burn-Up Wave in Epithermal Neutron Multiplying Medium

D. Ray, S. P. Saraswat, M. Kumar, O. P. Singh, P. Munshi
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2022, 8(2): 021501.
Paper No: NERS-20-1150
https://doi.org/10.1115/1.4049727
Published Online: October 19, 2021
View Article titled, Build Up and Characterization of Ultraslow Nuclear Burn-Up Wave in Epithermal Neutron Multiplying Medium
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Topics: Density, Neutrons, Steady state, Transients (Dynamics), Waves
Journal Articles

Numerical Verifications on Heat Transfer to Supercritical Water Flowing Upward in a 4-m Long Bare Vertical Tube

Dong Yang, Jiaxiang Chen, Yongchang Feng, Lin Chen
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2022, 8(2): 021402.
Paper No: NERS-20-1194
https://doi.org/10.1115/1.4051248
Published Online: October 19, 2021
View Article titled, Numerical Verifications on Heat Transfer to Supercritical Water Flowing Upward in a 4-m Long Bare Vertical Tube
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Topics: Heat transfer, Turbulence, Water, Temperature, Computer simulation, Heat flux, Heat, Density, Flow (Dynamics), Viscosity
Journal Articles

Superphénix Benchmark Part I: Results of Static Neutronics

Alexander Ponomarev, Konstantin Mikityuk, Liang Zhang, Evgeny Nikitin, Emil Fridman, Francisco Álvarez-Velarde, Pablo Romojaro Otero, Antonio Jiménez-Carrascosa, Nuria García-Herranz, Ben Lindley, Una Baker, Armin Seubert, Romain Henry
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2022, 8(1): 011320.
Paper No: NERS-21-1046
https://doi.org/10.1115/1.4051449
Published Online: October 8, 2021
View Article titled, Superphénix Benchmark Part I: Results of Static Neutronics
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Topics: Density, Fuels, Rods, Sodium, Temperature, Steel, Geometry, Cladding systems (Building), Neutrons, Chemical kinetics
Journal Articles

Global Sensitivity Analysis for U(VI) Transport for Integrating Coupled Thermal–Hydrological–Chemical Processes Models Into Performance Assessment Model

Dinara Ermakova, Haruko Wainwright, LianGe Zheng, Ian Shirley, Hannah Lu
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2021, 7(4): 041902.
Paper No: NERS-20-1174
https://doi.org/10.1115/1.4050297
Published Online: May 13, 2021
View Article titled, Global Sensitivity Analysis for U(VI) Transport for Integrating Coupled Thermal–Hydrological–Chemical Processes Models Into Performance Assessment Model
Open the PDF for Global Sensitivity Analysis for U(VI) Transport for Integrating Coupled Thermal–Hydrological–Chemical Processes Models Into Performance Assessment Model in another window
Topics: Polishing equipment, Rocks, Sensitivity analysis, Simulation, Chemical processes, Minerals, Density
Journal Articles

Backfill of Radioactive Waste Disposal: Feasibility Study of Argillite/Bentonite (COx/MX80) Pellets

Danai Tyri, Bui Quoc Huy Ly, François Nader, Irini Djeran-Maigre, Jean-Claude Robinet, Jad Zghondi
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2021, 7(4): 041901.
Paper No: NERS-20-1091
https://doi.org/10.1115/1.4050296
Published Online: April 22, 2021
View Article titled, Backfill of Radioactive Waste Disposal: Feasibility Study of Argillite/Bentonite (COx/MX80) Pellets
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Topics: Density, Pelletizing, Water, Machinery, Manufacturing, Stress, Optimization
Journal Articles

Serpent and Monte Carlo Continuous Energy Burnup Code Comparison for Neutronics Calculations of the European Lead-Cooled Fast Reactor

L. C. Juárez, J. I. Torres, J. L. François
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Technical Briefs
ASME J of Nuclear Rad Sci. July 2021, 7(3): 034505.
Paper No: NERS-20-1068
https://doi.org/10.1115/1.4049714
Published Online: April 1, 2021
View Article titled, Serpent and Monte Carlo Continuous Energy Burnup Code Comparison for Neutronics Calculations of the European Lead-Cooled Fast Reactor
Open the PDF for Serpent and Monte Carlo Continuous Energy Burnup Code Comparison for Neutronics Calculations of the European Lead-Cooled Fast Reactor in another window
Topics: Coolants, Density, Fast neutron reactors, Fuels, Neutrons, Cycles, Temperature, Modeling
Journal Articles

The Use of Polycarbonate as Dosimeter of High Doses

David Zoul, Markéta Koplová, Vít Rosnecký, Michal Košťál, Miroslav Vinš, Jan Šimon, Martin Schulc, Martin Cabalka, Jan Kučera, Vladimír Strunga
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2021, 7(2): 022003.
Paper No: NERS-20-1082
https://doi.org/10.1115/1.4049717
Published Online: February 19, 2021
View Article titled, The Use of Polycarbonate as Dosimeter of High Doses
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Topics: Dosimeters, Dosimetry, Irradiation (Radiation exposure), Neutrons, Radiation (Physics), Water, Wavelength, Gamma rays, Photons, Nuclear reactors
Journal Articles

Methodology for Measurement of Density of Liquid Oxides

Jan Hrbek, Bence Mészáros, Mykhaylo Paukov, Martin Kudláč
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2021, 7(2): 021601.
Paper No: NERS-20-1074
https://doi.org/10.1115/1.4048478
Published Online: November 16, 2020
View Article titled, Methodology for Measurement of Density of Liquid Oxides
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Topics: Density, Temperature, Electromagnetic induction, High temperature
Journal Articles

Formation of Local, Transient “Acid Spikes” in the Fast Neutron Radiolysis of Supercritical Water at 400 °C: A Potential Source of Corrosion in Supercritical Water-Cooled Reactors?

Md Mohsin Patwary, Sunuchakan Sanguanmith, Jintana Meesungnoen, Jean-Paul Jay-Gerin
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2020, 6(3): 031101.
Paper No: NERS-19-1048
https://doi.org/10.1115/1.4044409
Published Online: June 5, 2020
View Article titled, Formation of Local, Transient “Acid Spikes” in the Fast Neutron Radiolysis of Supercritical Water at 400 °C: A Potential Source of Corrosion in Supercritical Water-Cooled Reactors?
Open the PDF for Formation of Local, Transient “Acid Spikes” in the Fast Neutron Radiolysis of Supercritical Water at 400 °C: A Potential Source of Corrosion in Supercritical Water-Cooled Reactors? in another window
Topics: Neutrons, Water, Corrosion, Transients (Dynamics), Protons, Simulation, Chemistry, Density
Journal Articles

Study on Calculation Difference of the SCWR Core Steady-State Analysis Code

Lianjie Wang, Lei Yao, Ping Yang, Di Lu, Wenbo Zhao
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2020, 6(3): 031103.
Paper No: NERS-19-1054
https://doi.org/10.1115/1.4044408
Published Online: June 5, 2020
View Article titled, Study on Calculation Difference of the SCWR Core Steady-State Analysis Code
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Topics: Density, Feedback, Steady state, Supercritical water reactors, Thermal hydraulics, Water, Flow (Dynamics)