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Journal Articles

Spatial Distribution Assay of Active Neutron Counting

Yuqi Zhang, Xiaoming Xu, Yimei Cheng, Lixia He, Xiao Fan, Haocheng Zhao
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Technical Briefs
ASME J of Nuclear Rad Sci. April 2025, 11(2): 024501.
Paper No: NERS-24-1011
https://doi.org/10.1115/1.4066883
Published Online: November 22, 2024
View Article titled, Spatial Distribution Assay of Active Neutron Counting
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Topics: Neutrons, Nuclear fission, Simulation, Cavities, Fittings
Journal Articles

Performance of NB-CTMFD Detector Versus Ludlum 42-49B, and Fuji NSN3 Detectors for Hard (Am-Be) and Soft (Cf-252 Fission) Energy Spectra Neutron Sources Within Lead/Concrete Shielded Configurations

Yusuke Ota, Stepan Ozerov, Rusi 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): 042001.
Paper No: NERS-24-1035
https://doi.org/10.1115/1.4065852
Published Online: July 16, 2024
View Article titled, Performance of NB-CTMFD Detector Versus Ludlum 42-49B, and Fuji NSN3 Detectors for Hard (Am-Be) and Soft (Cf-252 Fission) Energy Spectra Neutron Sources Within Lead/Concrete Shielded Configurations
Open the PDF for Performance of NB-CTMFD Detector Versus Ludlum 42-49B, and Fuji NSN3 Detectors for Hard (Am-Be) and Soft (Cf-252 Fission) Energy Spectra Neutron Sources Within Lead/Concrete Shielded Configurations in another window
Topics: Concretes, Fluids, Neutrons, Sensors, Particulate matter, Neutron sources, Nuclear fission, Spectra (Spectroscopy), Simulation
Journal Articles

Validation Assessment of Turbulent Reacting Flow Model Using the Area-Validation Metric on Medium-Scale Methanol Pool Fire Results

Jared Kirsch, Nima Fathi
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2024, 10(4): 041701.
Paper No: NERS-23-1014
https://doi.org/10.1115/1.4065173
Published Online: May 10, 2024
View Article titled, Validation Assessment of Turbulent Reacting Flow Model Using the Area-Validation Metric on Medium-Scale Methanol Pool Fire Results
Open the PDF for Validation Assessment of Turbulent Reacting Flow Model Using the Area-Validation Metric on Medium-Scale Methanol Pool Fire Results in another window
Topics: Fire, Flames, Flow (Dynamics), Heat flux, Liquid pool fires, Methanol, Simulation, Temperature, Turbulence, Combustion
Journal Articles

Modeling of N and P-Type of Coaxial Ge Detectors Using MCNPX and the Effect of Dead Layer Variation on Its Response Function

R. A. El-Tayebany, Mohamed Ali, Nawal Mohmed, R. S. Mohamed
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Technical Briefs
ASME J of Nuclear Rad Sci. October 2024, 10(4): 044501.
Paper No: NERS-24-1003
https://doi.org/10.1115/1.4065395
Published Online: May 10, 2024
View Article titled, Modeling of N and P-Type of Coaxial Ge Detectors Using MCNPX and the Effect of Dead Layer Variation on Its Response Function
Open the PDF for Modeling of N and P-Type of Coaxial Ge Detectors Using MCNPX and the Effect of Dead Layer Variation on Its Response Function in another window
Topics: Sensors, Simulation, Dimensions
Journal Articles

Pearson Correlation and Chi-Squared Methods Applied to the Sensitivity and Uncertainty Analysis of Hydrogen Generation During a Boiling Water Reactor STSBO Using MAAP5 and AZTUSIA

Javier Ortiz-Villafuerte, Heriberto Sánchez-Mora, César Queral, Melisa Reyes-Fuentes, Edmundo del- Valle-Gallegos
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2024, 10(3): 031701.
Paper No: NERS-22-1021
https://doi.org/10.1115/1.4055011
Published Online: April 22, 2024
View Article titled, Pearson Correlation and Chi-Squared Methods Applied to the Sensitivity and Uncertainty Analysis of Hydrogen Generation During a Boiling Water Reactor STSBO Using MAAP5 and AZTUSIA
Open the PDF for Pearson Correlation and Chi-Squared Methods Applied to the Sensitivity and Uncertainty Analysis of Hydrogen Generation During a Boiling Water Reactor STSBO Using MAAP5 and AZTUSIA in another window
Topics: Boiling water reactors, Hydrogen, Oxidation, Simulation, Uncertainty analysis, Zirconium, Accidents, Sensitivity analysis, Temperature, Uncertainty
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

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

Computational Fluid Dynamics Calculations of Moderator Heat and Fluid Flow of Small Modular Heavy Water Reactor

Tomas Korinek, Radek Skoda, Martin Lovecky, Ondrej Burian
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Technical Briefs
ASME J of Nuclear Rad Sci. January 2024, 10(1): 014501.
Paper No: NERS-23-1015
https://doi.org/10.1115/1.4063007
Published Online: October 20, 2023
View Article titled, Computational Fluid Dynamics Calculations of Moderator Heat and Fluid Flow of Small Modular Heavy Water Reactor
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Topics: Computational fluid dynamics, Cooling systems, Flow (Dynamics), Fluid dynamics, Heat, Heavy water reactors, Inertia (Mechanics), Pressure, Temperature, Vessels
Journal Articles

Study of γ-Ray Spectrum Measurement Analysis Algorithm of Radioactive Solid Waste Steel Boxes

Yurong Li, Lixia He, Jing Wen, Jiewen Shao
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2024, 10(1): 012001.
Paper No: NERS-23-1027
https://doi.org/10.1115/1.4063039
Published Online: October 20, 2023
View Article titled, Study of γ-Ray Spectrum Measurement Analysis Algorithm of Radioactive Solid Waste Steel Boxes
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Topics: Algebra, Algorithms, Sensors, Simulation, Solid wastes, Steel, Radioactive wastes, Computerized tomography
Journal Articles

A Simple Analytical Model to Predict the Freeze Plug Opening Time in Molten Salt Reactors

Muhammad Ilham, Tomio Okawa
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Technical Briefs
ASME J of Nuclear Rad Sci. October 2023, 9(4): 041107.
Paper No: NERS-22-1162
https://doi.org/10.1115/1.4062879
Published Online: July 17, 2023
View Article titled, A Simple Analytical Model to Predict the Freeze Plug Opening Time in Molten Salt Reactors
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Topics: Molten salt reactors, Simulation, Wall thickness, Safety, Computer simulation, Design, Temperature, Heat conduction, Melting, Solidification
Journal Articles

Investigation Into Hybridization of the Two-Fluid Model and Phase-Field Model for Multi-Scale Two-Phase Flow Simulations

Akinori Tamura, Kenichi Katono
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2023, 9(3): 031404.
Paper No: NERS-22-1052
https://doi.org/10.1115/1.4055932
Published Online: February 8, 2023
View Article titled, Investigation Into Hybridization of the Two-Fluid Model and Phase-Field Model for Multi-Scale Two-Phase Flow Simulations
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Topics: Bubbles, Bubbly flow, Fluids, Pressure, Simulation, Plumes (Fluid dynamics), Porosity, Surface tension, Flow (Dynamics), Two-phase flow
Journal Articles

Introducing Passive Nuclear Safety in Water-Cooled Reactors: Numerical Simulation and Validation of Natural Convection Heat Transfer and Transport in Packed Beds of Heated Microspheres

Olugbenga O. Noah, Johan F. Slabber, Josua P. Meyer
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2023, 9(3): 031403.
Paper No: NERS-22-1020
https://doi.org/10.1115/1.4056239
Published Online: February 8, 2023
View Article titled, Introducing Passive Nuclear Safety in Water-Cooled Reactors: Numerical Simulation and Validation of Natural Convection Heat Transfer and Transport in Packed Beds of Heated Microspheres
Open the PDF for Introducing Passive Nuclear Safety in Water-Cooled Reactors: Numerical Simulation and Validation of Natural Convection Heat Transfer and Transport in Packed Beds of Heated Microspheres in another window
Topics: Fluids, Heat transfer, Particulate matter, Simulation, Temperature, Flow (Dynamics), Design, Fuels, Safety, Natural convection
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

Characterization of the Finite Element Computational Fluid Dynamics Capabilities in the Multiphysics Object Oriented Simulation Environment

Abdullah G. Weiss, Laith J. Zaidan, Mohammad T. H. Bani Ahmad, M. Gomaa Abdoelatef, John W. Peterson, Alexander D. Lindsay, Fande Kong, Karim Ahmed, Mark L. Kimber
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2023, 9(2): 021402.
Paper No: NERS-21-1170
https://doi.org/10.1115/1.4054685
Published Online: June 15, 2022
View Article titled, Characterization of the Finite Element Computational Fluid Dynamics Capabilities in the Multiphysics Object Oriented Simulation Environment
Open the PDF for Characterization of the Finite Element Computational Fluid Dynamics Capabilities in the Multiphysics Object Oriented Simulation Environment in another window
Topics: Computational fluid dynamics, Cylinders, Errors, Finite element analysis, Flow (Dynamics), Pressure, Simulation, Vortex street, Engineering simulation, Physics
Journal Articles

Theoretical Approach for the Fast Estimation of the Turbulent Kinematic Viscosity for Internal Flows

Sal Rodriguez, Nima Fathi, Mahyar Pourghasemi
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Technical Briefs
ASME J of Nuclear Rad Sci. July 2022, 8(3): 034502.
Paper No: NERS-20-1213
https://doi.org/10.1115/1.4054342
Published Online: May 26, 2022
View Article titled, Theoretical Approach for the Fast Estimation of the Turbulent Kinematic Viscosity for Internal Flows
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Topics: Flow (Dynamics), Internal flow, Kinematics, Turbulence, Viscosity, Simulation, Eddies (Fluid dynamics)
Journal Articles

Thermal-Hydraulic Safety Assessment of Full-Scale ESBWR Nuclear Reactor Design

S. P. Saraswat, D. Ray, G. Mishra, D. Yadav, V. S. Bhadouria, P. Munshi, C. Allison
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2022, 8(3): 031403.
Paper No: NERS-21-1073
https://doi.org/10.1115/1.4052014
Published Online: May 26, 2022
View Article titled, Thermal-Hydraulic Safety Assessment of Full-Scale ESBWR Nuclear Reactor Design
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Topics: Accidents, Boiling water reactors, Containment, Design, Pressure, Safety, Steam, Water, Heat, Economics
Journal Articles

Development of a Phase-Field Method for Phase Change Simulations Using a Conservative Allen–Cahn Equation

Akinori Tamura, Kenichi Katono
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2022, 8(3): 031402.
Paper No: NERS-21-1068
https://doi.org/10.1115/1.4052807
Published Online: May 26, 2022
View Article titled, Development of a Phase-Field Method for Phase Change Simulations Using a Conservative Allen–Cahn Equation
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Topics: Boundary-value problems, Simulation, Wetting, Vapors, Bubbles, Simulation results
Journal Articles

Development and Processing of Thermal-Hydraulic Model for GFR 2400 Fast Reactor Design and NESTLE Coupled Transient Code

Filip Osuský, Branislav Vrban, Štefan Čerba, Jakub Lüley, 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): 041401.
Paper No: NERS-21-1012
https://doi.org/10.1115/1.4051515
Published Online: March 22, 2022
View Article titled, Development and Processing of Thermal-Hydraulic Model for GFR 2400 Fast Reactor Design and NESTLE Coupled Transient Code
Open the PDF for Development and Processing of Thermal-Hydraulic Model for GFR 2400 Fast Reactor Design and NESTLE Coupled Transient Code in another window
Topics: Coolants, Design, Fast neutron reactors, Fuels, Heat, Temperature, Transients (Dynamics), Temperature distribution, Simulation, Cladding systems (Building)
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
Open the PDF for Flow and Heat Transfer Simulation in a Complete Pressurized Water Reactor Fuel Assembly Using Wall-Modeled RANS in another window
Topics: Flow (Dynamics), Fuel rods, Fuels, Manufacturing, Pressure drop, Pressurized water reactors, Temperature, Simulation, Reynolds-averaged Navier–Stokes equations, Turbulence
Journal Articles

Development of a Phase-Field Method for Phase Change Simulations Using a Conservative Allen–Cahn Equation

Akinori Tamura, Kenichi Katono
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2022, 8(2): 021401.
Paper No: NERS-20-1182
https://doi.org/10.1115/1.4050209
Published Online: October 19, 2021
View Article titled, Development of a Phase-Field Method for Phase Change Simulations Using a Conservative Allen–Cahn Equation
Open the PDF for Development of a Phase-Field Method for Phase Change Simulations Using a Conservative Allen–Cahn Equation in another window
Topics: Boundary-value problems, Simulation, Wetting, Vapors, Bubbles, Simulation results