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Journal Articles

Investigation of Metal-H 2 O Systems at Elevated Temperatures: Part II. SnO 2(s) Solubility Data and New Sn Pourbaix Diagrams at 298.15 K and 358.15 K

Olga Y. Palazhchenko, Matthew H. Kaye
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2025, 11(2): 021601.
Paper No: NERS-23-1111
https://doi.org/10.1115/1.4066340
Published Online: September 30, 2024
View Article titled, Investigation of Metal-H 2 O Systems at Elevated Temperatures: Part II. SnO 2(s) Solubility Data and New Sn Pourbaix Diagrams at 298.15 K and 358.15 K
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Topics: Temperature, Tin, Equilibrium (Physics)
Journal Articles

Monitoring for Actinide Neutron Emissions From Spent Nuclear Fuel Under Extreme Gamma Fields Using Centrifugally Tensioned Metastable Fluid Detector Sensor Technology

C. Harabagiu, R. P. Taleyarkhan
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2024, 10(4): 041601.
Paper No: NERS-23-1119
https://doi.org/10.1115/1.4065280
Published Online: May 10, 2024
View Article titled, Monitoring for Actinide Neutron Emissions From Spent Nuclear Fuel Under Extreme Gamma Fields Using Centrifugally Tensioned Metastable Fluid Detector Sensor Technology
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Topics: Fluids, Neutrons, Sensors, Emissions, Photons, Spent nuclear fuels
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

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

Thermomechanical Performance Assessment of U-Mo Monolithic Fuel Plates With Zircaloy Cladding

Hakan Ozaltun, James I. Cole, Barry H. Rabin
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2024, 10(2): 021601.
Paper No: NERS-23-1048
https://doi.org/10.1115/1.4063163
Published Online: November 1, 2023
View Article titled, Thermomechanical Performance Assessment of U-Mo Monolithic Fuel Plates With Zircaloy Cladding
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Topics: Cladding systems (Building), Fuels, Stress, Temperature, Irradiation (Radiation exposure), Plates (structures), Deformation
Journal Articles

Uranium Price Expectations and Stabilization Policy Formation in the Manhattan Project: An Institutional Economics Approach

Alberto D'Ansi Mendoza España
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2023, 9(3): 031601.
Paper No: NERS-22-1023
https://doi.org/10.1115/1.4055585
Published Online: February 8, 2023
View Article titled, Uranium Price Expectations and Stabilization Policy Formation in the Manhattan Project: An Institutional Economics Approach
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Topics: Uranium, Economics
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

The Heat Capacity of PuO 2 at High Temperature: Molecular Dynamics Calculations

Rolando Calabrese
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2022, 8(4): 041603.
Paper No: NERS-21-1027
https://doi.org/10.1115/1.4054941
Published Online: September 1, 2022
View Article titled, The Heat Capacity of PuO 2 at High Temperature: Molecular Dynamics Calculations
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Topics: Heat capacity, High temperature, Oxygen, Temperature, Molecular dynamics, Enthalpy, Modeling
Journal Articles

Coupling of ASTEC V2.1 and RASCAL 4.3 Codes to Evaluate the Source Term and the Radiological Consequences of a Loss-of-Cooling Accident at a Spent Fuel Pool

Antonio Guglielmelli, Stefano Ederli, Fulvio Mascari, Federico Rocchi, Pietro Maccari
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2022, 8(4): 041602.
Paper No: NERS-21-1018
https://doi.org/10.1115/1.4054514
Published Online: June 24, 2022
View Article titled, Coupling of ASTEC V2.1 and RASCAL 4.3 Codes to Evaluate the Source Term and the Radiological Consequences of a Loss-of-Cooling Accident at a Spent Fuel Pool
Open the PDF for Coupling of ASTEC V2.1 and RASCAL 4.3 Codes to Evaluate the Source Term and the Radiological Consequences of a Loss-of-Cooling Accident at a Spent Fuel Pool in another window
Topics: Accidents, Cooling, Emissions, Fukushima nuclear disaster, Japan, 2011, Meteorology, Nuclear power stations, Simulation, Spent nuclear fuels, Wind, Wind velocity
Journal Articles

Steady-State Subchannel Thermalhydraulic Assessment of a Full-Scale Pressurized Water Reactor-Small Modular Reactor Fuel Assembly With Conventional and Advanced Fuels

Ayman M. Bayomy, Blair P. Bromley, Armando Nava Dominguez, Samuel Kelly
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2022, 8(3): 031601.
Paper No: NERS-21-1184
https://doi.org/10.1115/1.4053829
Published Online: June 1, 2022
View Article titled, Steady-State Subchannel Thermalhydraulic Assessment of a Full-Scale Pressurized Water Reactor-Small Modular Reactor Fuel Assembly With Conventional and Advanced Fuels
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Topics: Fuels, Manufacturing, Temperature, Water
Journal Articles

Fuel Performance Modeling at High Burn-Up by FEMAXI-6 Code

Jakub Lüley, Branislav Vrban, Štefan Čerba, Filip Osuský, Vladimír Nečas
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2022, 8(4): 041601.
Paper No: NERS-21-1030
https://doi.org/10.1115/1.4052519
Published Online: March 22, 2022
View Article titled, Fuel Performance Modeling at High Burn-Up by FEMAXI-6 Code
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Topics: Fuels, Grain size, Irradiation (Radiation exposure), Modeling, Nuclear fission, Rods, Pressure, Cladding systems (Building), Stress
Journal Articles

Hybrid Reactivity-Equivalent Physical Transformation Method on Double-Heterogeneous System Containing Dispersed Fuel Particles and Burnable Poison Particles

Lei Lou, Xiaoming Chai, Dong Yao, Xingjie Peng, Mancang Li, Liang Chen, Yingrui Yu, Lianjie Wang
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2022, 8(2): 021601.
Paper No: NERS-20-1025
https://doi.org/10.1115/1.4051724
Published Online: October 19, 2021
View Article titled, Hybrid Reactivity-Equivalent Physical Transformation Method on Double-Heterogeneous System Containing Dispersed Fuel Particles and Burnable Poison Particles
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Topics: Fuels, Particulate matter
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

Best Practices and Lessons Learned From Nuclear Materials Retrieval Programs of the United States Department of Energy

Kaatrin Abbott, Zachary Geroux
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2021, 7(4): 041603.
Paper No: NERS-20-1098
https://doi.org/10.1115/1.4049052
Published Online: April 22, 2021
View Article titled, Best Practices and Lessons Learned From Nuclear Materials Retrieval Programs of the United States Department of Energy
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Topics: Uranium, Governments, Ships, Teams
Journal Articles

Metallic Fast Reactor Separate Effect Studies for Fuel Safety

Fidelma G. Di Lemma, Colby B. Jensen, Joshua J. Kane, Wei-Ying Chen, Xiang Liu, Luca Capriotti, Cynthia A. Adkins, Boopathy Kombaiah, Alexander J. Winston, Lingfeng He, Daniel Wachs
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2021, 7(4): 041602.
Paper No: NERS-20-1097
https://doi.org/10.1115/1.4049721
Published Online: April 22, 2021
View Article titled, Metallic Fast Reactor Separate Effect Studies for Fuel Safety
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Topics: Bubbles, Fuels, Instrumentation, Irradiation (Radiation exposure), Nuclear fission, Safety, Transients (Dynamics), Sodium fast reactors, Testing, Fast neutron reactors
Journal Articles

Comparative Study of Physical Models for Particle Sedimentation Using SIMMER Code

Eszter Csengeri, Andrea Bachrata, Laurent Trotignon, Elsa Merle
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2021, 7(4): 041601.
Paper No: NERS-20-1122
https://doi.org/10.1115/1.4049197
Published Online: April 16, 2021
View Article titled, Comparative Study of Physical Models for Particle Sedimentation Using SIMMER Code
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Topics: Particulate matter, Sodium
Journal Articles

Experimental and Numerical Investigation of Solidification of Gallium in an Initially Emptied Horizontal Pipe Flow

Shawn Somers-Neal, Alex Pegarkov, 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. July 2021, 7(3): 031602.
Paper No: NERS-20-1052
https://doi.org/10.1115/1.4049096
Published Online: March 16, 2021
View Article titled, Experimental and Numerical Investigation of Solidification of Gallium in an Initially Emptied Horizontal Pipe Flow
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Topics: Gallium, Metals, Pipes, Solidification, Temperature, Computer simulation, Reynolds number, Flow (Dynamics), Wall temperature
Journal Articles

Effect of Sequential Helium and Nickel Ion Implantation on the Nano-Indentation Hardness of X750 Alloy

Maisaa N. Tawfeeq, Robert J. Klassen
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2021, 7(3): 031601.
Paper No: NERS-19-1146
https://doi.org/10.1115/1.4049095
Published Online: March 16, 2021
View Article titled, Effect of Sequential Helium and Nickel Ion Implantation on the Nano-Indentation Hardness of X750 Alloy
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Topics: Alloys, Helium, Ion implantation, Temperature, Nanoindentation, Bubbles, Hardening, Nickel, Heat, Damage
Journal Articles

Pressurized Water Reactor Mixed Oxide/UO 2 Transient Benchmark Calculations Using Monte Carlo Serpent 2 Code and Open Nodal Core Simulator ADPRES

Muhammad Imron, Donny Hartanto
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2021, 7(3): 031603.
Paper No: NERS-20-1064
https://doi.org/10.1115/1.4048764
Published Online: March 16, 2021
View Article titled, Pressurized Water Reactor Mixed Oxide/UO 2 Transient Benchmark Calculations Using Monte Carlo Serpent 2 Code and Open Nodal Core Simulator ADPRES
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Topics: Boron, Coordinate measuring machines, Cross section (Physics), Fuels, Manufacturing, Pressurized water reactors, Transients (Dynamics), Temperature, Diffusion (Physics), Geometry
Journal Articles

Comparison of Corrosion Behavior of the Austenitic Stainless Steel 316 L in Static and Flowing Liquid Lead

Lucia Rozumová, Lukáš Košek, Jan Vít, Anna Hojná, Patricie Halodová
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2021, 7(2): 021605.
Paper No: NERS-20-1096
https://doi.org/10.1115/1.4049719
Published Online: February 19, 2021
View Article titled, Comparison of Corrosion Behavior of the Austenitic Stainless Steel 316 L in Static and Flowing Liquid Lead
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Topics: Corrosion, Oxygen, Stainless steel, Steel