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Journal Articles

A Mathematical Model Design for Pu Content Analyzed by 244 Cm in Spent Fuel of Fast Reactors

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Jinlei Zhao, Lixia He, Haocheng Zhao, Yuqi Zhang, Wentao Li
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2025, 11(3): 031002.
Paper No: NERS-24-1087
https://doi.org/10.1115/1.4067824
Published Online: February 26, 2025
View Articletitled, A Mathematical Model Design for Pu Content Analyzed by 244 Cm in Spent Fuel of Fast Reactors
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Topics: Errors, Fast neutron reactors, Fuels, Liquid metal fast breeder reactors, Neutrons, Regression models, Spent nuclear fuels, Uranium, Cooling, Simulation
Journal Articles

K-Edge Measurement Technology Simulation Model Design

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Wen-Tao Li, Li-Xia He, Lei Bai, Xiao Zhao, Yu-Qi Zhang, Hao-Cheng Zhao
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Technical Briefs
ASME J of Nuclear Rad Sci. July 2025, 11(3): 034502.
Paper No: NERS-24-1081
https://doi.org/10.1115/1.4067724
Published Online: February 14, 2025
View Articletitled, K-Edge Measurement Technology Simulation Model Design
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Topics: Absorption, Calibration, Light sources, Photons, Sensors, Uranium, X-rays, Germanium, Simulation models, Design
Journal Articles

Review of Canadian Experience With the Fabrication of Thoria-Based Fuels for Advanced Reactors and Fuel Cycles for Long-Term Nuclear Energy Sustainability and Security

Open Access
Germán Cota-Sanchez, Madalena S. Spencer, Kristin Leeder, Ike Dimayuga, Blair P. Bromley
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2025, 11(2): 021604.
Paper No: NERS-24-1048
https://doi.org/10.1115/1.4067304
Published Online: December 20, 2024
View Articletitled, Review of Canadian Experience With the Fabrication of Thoria-Based Fuels for Advanced Reactors and Fuel Cycles for Long-Term Nuclear Energy Sustainability and Security
Open the PDF for Review of Canadian Experience With the Fabrication of Thoria-Based Fuels for Advanced Reactors and Fuel Cycles for Long-Term Nuclear Energy Sustainability and Security in another window
Topics: Fuels, Manufacturing, Density, Sintering, Uranium, Milling
Journal Articles

Evaluating Hydrogen-Based Moderators in High-Temperature Gas-Cooled Reactors With 5 wt.% Enriched Uranium Annular Fuel Rods

Open Access
Daniel T. Wojtaszek, Blair P. Bromley
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2024, 10(3): 031302.
Paper No: NERS-23-1090
https://doi.org/10.1115/1.4064581
Published Online: April 17, 2024
View Articletitled, Evaluating Hydrogen-Based Moderators in High-Temperature Gas-Cooled Reactors With 5 wt.% Enriched Uranium Annular Fuel Rods
Open the PDF for Evaluating Hydrogen-Based Moderators in High-Temperature Gas-Cooled Reactors With 5 wt.% Enriched Uranium Annular Fuel Rods in another window
Topics: Fuels, Hydrogen, Temperature, Very high temperature reactors, Uranium, Manufacturing
Journal Articles

9 MV LINAC Photoneutron Interrogation of Uranium With Advanced Acoustically Tensioned Metastable Fluid Detectors

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Nathan Boyle, Stepan Ozerov, Catalin Harabagiu, Rusi P. Taleyarkhan
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2023, 9(4): 042001.
Paper No: NERS-23-1033
https://doi.org/10.1115/1.4062951
Published Online: September 15, 2023
View Articletitled, 9 MV LINAC Photoneutron Interrogation of Uranium With Advanced Acoustically Tensioned Metastable Fluid Detectors
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Topics: Acoustics, Fluids, Neutrons, Photons, Sensors, Vacuum, Uranium, X-rays
Journal Articles

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

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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 Articletitled, 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

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

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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 Articletitled, Uranium Price Expectations and Stabilization Policy Formation in the Manhattan Project: An Institutional Economics Approach
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Topics: Uranium, Economics
Journal Articles

Physics Evaluation of Alternative Uranium-Based Oxy-Carbide Annular Fuel Concepts for Potential Use in Compact High-Temperature Gas-Cooled Reactors

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Daniel T. Wojtaszek, Blair P. Bromley
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2023, 9(1): 011504.
Paper No: NERS-22-1009
https://doi.org/10.1115/1.4055009
Published Online: September 13, 2022
View Articletitled, Physics Evaluation of Alternative Uranium-Based Oxy-Carbide Annular Fuel Concepts for Potential Use in Compact High-Temperature Gas-Cooled Reactors
Open the PDF for Physics Evaluation of Alternative Uranium-Based Oxy-Carbide Annular Fuel Concepts for Potential Use in Compact High-Temperature Gas-Cooled Reactors in another window
Topics: Fuels, Uranium, Neutrons
Journal Articles

Physics Assessment of the Impact of Modified End Pellets on Axial Power Peaking for Advanced/Nonconventional Uranium-Based Fuels in Pressure Tube Heavy Water Reactors

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Huiping V. Yan, Blair P. Bromley
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2023, 9(1): 011503.
Paper No: NERS-21-1179
https://doi.org/10.1115/1.4054841
Published Online: September 1, 2022
View Articletitled, Physics Assessment of the Impact of Modified End Pellets on Axial Power Peaking for Advanced/Nonconventional Uranium-Based Fuels in Pressure Tube Heavy Water Reactors
Open the PDF for Physics Assessment of the Impact of Modified End Pellets on Axial Power Peaking for Advanced/Nonconventional Uranium-Based Fuels in Pressure Tube Heavy Water Reactors in another window
Topics: Fuels, Heavy water reactors, Uranium
Journal Articles

Radon and Exhalation Rate Measurement of Soil Samples in Al-Amiriya Area in Baghdad Governorate Using a Nuclear Track Detector

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Basim Khalaf Rejah
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Technical Briefs
ASME J of Nuclear Rad Sci. January 2023, 9(1): 014501.
Paper No: NERS-22-1001
https://doi.org/10.1115/1.4054619
Published Online: June 7, 2022
View Articletitled, Radon and Exhalation Rate Measurement of Soil Samples in Al-Amiriya Area in Baghdad Governorate Using a Nuclear Track Detector
Open the PDF for Radon and Exhalation Rate Measurement of Soil Samples in Al-Amiriya Area in Baghdad Governorate Using a Nuclear Track Detector in another window
Topics: Sensors, Soil, Uranium, Nuclear track detectors, Bridges (Structures), Rocks, Radiation (Physics), Water
Journal Articles

Estimating Radon Excess Lung Cancer at the Babylon Cement Plant in Iraq

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Israa Kamil Ahmed, Hyam Nazmy Bader Khalaf, Mostafa Y. A. Mostafa
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2022, 8(3): 032003.
Paper No: NERS-20-1181
https://doi.org/10.1115/1.4049757
Published Online: May 27, 2022
View Articletitled, Estimating Radon Excess Lung Cancer at the Babylon Cement Plant in Iraq
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Topics: Cancer, Cement plants, Lung, Soil, Uranium, Sensors
Journal Articles

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

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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 Articletitled, 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

Radiological Risk Assessment of Radon Gas in Bricks Samples in Iraq

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Ali Abid Abojassim
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2021, 7(3): 032001.
Paper No: NERS-20-1022
https://doi.org/10.1115/1.4049051
Published Online: March 16, 2021
View Articletitled, Radiological Risk Assessment of Radon Gas in Bricks Samples in Iraq
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Topics: Bricks, Uranium, Radium, Risk, Radiation (Physics), Cancer, Risk assessment
Journal Articles

Testing and Validation of Nuclear Fuel Composition Using SIMS Method

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Ivan Elantyev, Michal Kostal, Evzen Losa, Kristina Sihelska, Klara Rezankova, Jan Lorincik
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2021, 7(2): 022002.
Paper No: NERS-20-1155
https://doi.org/10.1115/1.4049097
Published Online: January 28, 2021
View Articletitled, Testing and Validation of Nuclear Fuel Composition Using SIMS Method
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Topics: Particulate matter, Secondary ion mass spectrometry, Uranium, Fuels, Nuclear fuels, Testing
Journal Articles

Finite Element Model of a Melting Terminal Debris Bed in a CANDU Calandria

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R. David
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2021, 7(1): 011703.
Paper No: NERS-19-1184
https://doi.org/10.1115/1.4048008
Published Online: October 5, 2020
View Articletitled, Finite Element Model of a Melting Terminal Debris Bed in a CANDU Calandria
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Topics: Accidents, Finite element model, Heat, Melting, Porosity, Temperature, Transients (Dynamics), Uranium, Materials properties
Journal Articles

The Other Metallic Phase in Spent Nuclear Fuel: A Complete Thermodynamic Evaluation of the U–Pd–Rh–Ru System

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Lian-Cheng Wang, Matthew H. Kaye
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2021, 7(1): 011601.
Paper No: NERS-19-1094
https://doi.org/10.1115/1.4046784
Published Online: October 1, 2020
View Articletitled, The Other Metallic Phase in Spent Nuclear Fuel: A Complete Thermodynamic Evaluation of the U–Pd–Rh–Ru System
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Topics: Nuclear fuels, Phase diagrams, Temperature, Uranium, Modeling, Military systems, Nuclear fission, Spent nuclear fuels
Journal Articles

Determination of β eff for ININ ' s TRIGA Reactor

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J. Galicia-Aragón, R. Raya-Arredondo, H. S. Cruz-Galindo
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2020, 6(3): 031502.
Paper No: NERS-19-1084
https://doi.org/10.1115/1.4046355
Published Online: May 15, 2020
View Articletitled, Determination of β eff for ININ ' s TRIGA Reactor
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Topics: Fuels, Neutrons, Isotopes, Uranium, Particulate matter
Journal Articles

The Impact of Fueling Operations on Full Core Uncertainty Analysis in CANDU Reactors

Open Access
M. D. Tucker, D. R. Novog
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2020, 6(3): 031401.
Paper No: NERS-19-1065
https://doi.org/10.1115/1.4045485
Published Online: March 9, 2020
View Articletitled, The Impact of Fueling Operations on Full Core Uncertainty Analysis in CANDU Reactors
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Topics: Algorithms, Cross section (Physics), Feedback, Fuels, Simulation, Uncertainty, Uncertainty analysis, Uranium, Physics, Diffusion (Physics)
Journal Articles

Preparation of UF 4 by Carbochlorination of U 3 O 8 and Solid-State Halogen Exchange Reaction

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Cristina N. Guibaldo, Georgina De Micco, Ana E. Bohé
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2019, 5(2): 020910.
Paper No: NERS-18-1066
https://doi.org/10.1115/1.4042362
Published Online: March 15, 2019
View Articletitled, Preparation of UF 4 by Carbochlorination of U 3 O 8 and Solid-State Halogen Exchange Reaction
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Topics: Uranium, Carbon, Quartz, X-ray diffraction
Journal Articles

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

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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 Articletitled, 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