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Journal Articles

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

Accepted Manuscript
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.
Paper No: NERS-24-1028
https://doi.org/10.1115/1.4066523
Published Online: September 13, 2024
View Article titled, Studies of the Thermalhydraulics Subchannel Code ASSERT-PV 3.2-SC for Supercritical Applications
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Topics: Computers, Fuels, Manufacturing, Nuclear fuels, Nuclear industry, Supercritical fluids, Water
Journal Articles

TSUNAMI Analyses of the Similarity and Applicability of ZED-2 Critical Experiments for Reactor Physics Code Benchmarking for a Pressurized Water Reactor Small Modular Reactor (PWR-SMR) Design Concept

Accepted Manuscript
Eugene Masala, Laura Blomeley, David G. Watts, Blair Bromley
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci.
Paper No: NERS-24-1016
https://doi.org/10.1115/1.4066404
Published Online: September 2, 2024
View Article titled, TSUNAMI Analyses of the Similarity and Applicability of ZED-2 Critical Experiments for Reactor Physics Code Benchmarking for a Pressurized Water Reactor Small Modular Reactor (PWR-SMR) Design Concept
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Topics: Design, Physics, Pressurized water reactors, Small modular reactors, Tsunamis, Fuels, Water, Boron, Gadolinium, Manufacturing
Journal Articles

Estimation of Turbulent Mixing Factor and Study of Turbulent Flow Structures in PWR Sub Channel by DNS

Accepted Manuscript
Raj Kumar Singh, Deb Mukhopadhyay, Devang Khakhar, J. B. Joshi
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci.
Paper No: NERS-24-1004
https://doi.org/10.1115/1.4066001
Published Online: July 20, 2024
View Article titled, Estimation of Turbulent Mixing Factor and Study of Turbulent Flow Structures in PWR Sub Channel by DNS
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Topics: Pressurized water reactors, Turbulence, Computational fluid dynamics, Design, Computer simulation, Dynamics (Mechanics), Equilibrium (Physics), Fuels, Geometry, Momentum
Journal Articles

Effect of Radial Neutron Reflector on the Characteristics of Nuclear Fuel Burn-Up Wave in a Fast Neutron Energy Spectrum Multiplying Medium: A Consistent Parametric Approach

Dipanjan Ray, Satya Prakash Saraswat, Vikesh Singh Bhadouria
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2024, 10(4): 041501.
Paper No: NERS-23-1097
https://doi.org/10.1115/1.4065893
Published Online: July 16, 2024
View Article titled, Effect of Radial Neutron Reflector on the Characteristics of Nuclear Fuel Burn-Up Wave in a Fast Neutron Energy Spectrum Multiplying Medium: A Consistent Parametric Approach
Open the PDF for Effect of Radial Neutron Reflector on the Characteristics of Nuclear Fuel Burn-Up Wave in a Fast Neutron Energy Spectrum Multiplying Medium: A Consistent Parametric Approach in another window
Topics: Diffusion (Physics), Fuels, Geometry, Neutron flux, Neutrons, Scalars, Waves, Nuclear fuels, Design, Transients (Dynamics)
Journal Articles

The Transfer of Xenon-135 to Molten Salt Reactor Graphite

Terry Price, Ondrej Chvala
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2024, 10(4): 041001.
Paper No: NERS-22-1113
https://doi.org/10.1115/1.4064464
Published Online: June 21, 2024
View Article titled, The Transfer of Xenon-135 to Molten Salt Reactor Graphite
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Topics: Graphite, Porosity, Fuels, Molten salt reactors, Mass transfer, Diffusion (Physics)
Journal Articles

Legal Issues of Fusion Technologies

Nataliia Aksenova
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2025, 11(1): 012203.
Paper No: NERS-23-1065
https://doi.org/10.1115/1.4065066
Published Online: May 10, 2024
View Article titled, Legal Issues of Fusion Technologies
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Topics: Liabilities, Nuclear fusion, Nuclear power, Radioactive wastes, Regulations, Safety, Nuclear fission, Licensing, Fuels
Journal Articles

Revenue Requirements Method for Assessing the Cost Impact of Fuel Cladding Corrosion in a Supercritical Water-Cooled Small Modular Reactor: A Methodological Review on Life Cycle Costing Corrosion

Alberto D'Ansi Mendoza España
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Review Articles
ASME J of Nuclear Rad Sci. October 2024, 10(4): 040801.
Paper No: NERS-23-1077
https://doi.org/10.1115/1.4064639
Published Online: May 10, 2024
View Article titled, Revenue Requirements Method for Assessing the Cost Impact of Fuel Cladding Corrosion in a Supercritical Water-Cooled Small Modular Reactor: A Methodological Review on Life Cycle Costing Corrosion
Open the PDF for Revenue Requirements Method for Assessing the Cost Impact of Fuel Cladding Corrosion in a Supercritical Water-Cooled Small Modular Reactor: A Methodological Review on Life Cycle Costing Corrosion in another window
Topics: Cladding systems (Building), Corrosion, Fuels, Supercritical water reactors, Water
Journal Articles

Verification and Geometry Optimization of a One Fluid Molten Salt Reactor With Fixed Volume

R. Andika Putra Dwijayanto, Harun Ardiansyah, Andang Widi Harto
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2024, 10(3): 031301.
Paper No: NERS-23-1088
https://doi.org/10.1115/1.4064465
Published Online: April 17, 2024
View Article titled, Verification and Geometry Optimization of a One Fluid Molten Salt Reactor With Fixed Volume
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Topics: Fluids, Fuels, Geometry, Molten salt reactors, Neutrons, Optimization, Temperature
Journal Articles

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

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 Article titled, Evaluating Hydrogen-Based Moderators in High-Temperature Gas-Cooled Reactors With 5 wt.% Enriched Uranium Annular Fuel Rods
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Topics: Fuels, Hydrogen, Temperature, Very high temperature reactors, Uranium, Manufacturing
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

Implementation of Solar Salt Properties Into ARIANT and Simulation of Pressurized Loss of Forced Circulation in a High Temperature Gas-Cooled Small Modular Reactor

Jason H. Wu, Thomas G. Beuthe, Aleksandar Vasić
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2024, 10(3): 030905.
Paper No: NERS-23-1051
https://doi.org/10.1115/1.4062917
Published Online: March 8, 2024
View Article titled, Implementation of Solar Salt Properties Into ARIANT and Simulation of Pressurized Loss of Forced Circulation in a High Temperature Gas-Cooled Small Modular Reactor
Open the PDF for Implementation of Solar Salt Properties Into ARIANT and Simulation of Pressurized Loss of Forced Circulation in a High Temperature Gas-Cooled Small Modular Reactor in another window
Topics: Heat, Simulation, Solar energy, Temperature, High temperature, Helium, Fuels, Coolants, Fluids, Small modular reactors
Journal Articles

Technical Brief: Safeguardability Analysis of a Molten Salt Sampling System Design

Megan Harkema, Steven Krahn, Paul Marotta
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2024, 10(3): 030903.
Paper No: NERS-23-1041
https://doi.org/10.1115/1.4064343
Published Online: March 8, 2024
View Article titled, Technical Brief: Safeguardability Analysis of a Molten Salt Sampling System Design
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Topics: Design, Fuels, Molten salt reactors, Engineering prototypes
Journal Articles

Feasibility Study on the Application of Boron Carbide for Long Term Reactivity Control in the LOTUS Small Fast Reactor

Thanh Mai Vu, Thi Hong Bui, Le Quang Linh Tran
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2024, 10(2): 021503.
Paper No: NERS-23-1046
https://doi.org/10.1115/1.4063739
Published Online: January 29, 2024
View Article titled, Feasibility Study on the Application of Boron Carbide for Long Term Reactivity Control in the LOTUS Small Fast Reactor
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Topics: Control systems, Design, Fast neutron reactors, Fuels, Neutrons, Rods, Coolants, Boron, Absorption, Safety
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

A Monte Carlo Fuel Assembly Model Validation Adopting Post Irradiation Experiment Dataset

Lorenzo Loi, Stefano Lorenzi, Antonio Cammi, Carolina Introini
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Technical Briefs
ASME J of Nuclear Rad Sci. January 2024, 10(1): 014502.
Paper No: NERS-23-1029
https://doi.org/10.1115/1.4064308
Published Online: December 22, 2023
View Article titled, A Monte Carlo Fuel Assembly Model Validation Adopting Post Irradiation Experiment Dataset
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Topics: Cycles, Fuels, Irradiation (Radiation exposure), Manufacturing, Nuclides, Simulation, Temperature, Uncertainty, Geometry, Errors
Journal Articles

Special Experimental Environment for Generation IV Reactors With Graphite Reflector

Eva Vilímová, Tomáš Peltan, Radek Škoda
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2024, 10(1): 011501.
Paper No: NERS-23-1017
https://doi.org/10.1115/1.4064124
Published Online: December 19, 2023
View Article titled, Special Experimental Environment for Generation IV Reactors With Graphite Reflector
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Topics: Graphite, Neutron flux, Neutrons, Fuels
Journal Articles

Assessment of Reactor Physics Characteristics of Prismatic Fuel Concepts With a Hydrogen-Based Moderator for Use in a Fluoride Salt-Cooled Small Modular Reactor

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. April 2024, 10(2): 021502.
Paper No: NERS-23-1010
https://doi.org/10.1115/1.4063388
Published Online: November 1, 2023
View Article titled, Assessment of Reactor Physics Characteristics of Prismatic Fuel Concepts With a Hydrogen-Based Moderator for Use in a Fluoride Salt-Cooled Small Modular Reactor
Open the PDF for Assessment of Reactor Physics Characteristics of Prismatic Fuel Concepts With a Hydrogen-Based Moderator for Use in a Fluoride Salt-Cooled Small Modular Reactor in another window
Topics: Coolants, Fuels, Temperature, Hydrogen, Graphite, Design, Rods, Physics
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

Depletion Calculations for an Integral Small Molten Salt Reactor With Serpent

Xiaolin Wang, T. Sinh Nguyen, Daniel Wojtaszek
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2024, 10(2): 021301.
Paper No: NERS-23-1004
https://doi.org/10.1115/1.4063111
Published Online: October 20, 2023
View Article titled, Depletion Calculations for an Integral Small Molten Salt Reactor With Serpent
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Topics: Fuels, Molten salt reactors, Flow (Dynamics), Cycles, Nuclear fission
Journal Articles

Experimental Investigation of Control Rod Drops Into Perturbed Fuel Assemblies

Namgyu Park, Ohjoon Kwon, Youngik Yoo, Taesoon Kim
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2023, 9(4): 041801.
Paper No: NERS-23-1003
https://doi.org/10.1115/1.4062275
Published Online: September 15, 2023
View Article titled, Experimental Investigation of Control Rod Drops Into Perturbed Fuel Assemblies
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Topics: Deformation, Fuels, Manufacturing, Impact testing, Buckling