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Journal Articles

Effect of Variable Angular Piping Bends Geometry on Turbulent Flow of Supercritical Water in an SCWR Plant Piping Network: A Three-Dimensional Computational Fluid Dynamics Investigation

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Mohammad Khan, Jehad Haque, Saad Islam, Lubon Putul, Mehedi Hasan
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2025, 11(3): 031401.
Paper No: NERS-24-1060
https://doi.org/10.1115/1.4067628
Published Online: February 14, 2025
View Articletitled, Effect of Variable Angular Piping Bends Geometry on Turbulent Flow of Supercritical Water in an SCWR Plant Piping Network: A Three-Dimensional Computational Fluid Dynamics Investigation
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Topics: Computational fluid dynamics, Flow (Dynamics), Pipe bends, Pipes, Pressure, Supercritical water reactors, Turbulence, Water, Geometry, Fluids
Journal Articles

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

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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. April 2025, 11(2): 021402.
Paper No: NERS-24-1028
https://doi.org/10.1115/1.4066523
Published Online: November 4, 2024
View Articletitled, Studies of the Thermalhydraulics Subchannel Code ASSERT-PV 3.2-SC for Supercritical Applications
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Topics: Flow (Dynamics), Fluids, Fuels, Heat transfer, Manufacturing, Pressure, Supercritical water reactors, Wall temperature, Water, Wire
Journal Articles

Performance of Borated Centrifugally Tensioned Metastable Fluid Detector Versus Ludlum 42-49B, Fuji NSN3 Detectors for Fission Energy Spectrum Neutron Detection With the Source Within Lead/Concrete Shielded Configurations

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Yusuke Ota, 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): 042002.
Paper No: NERS-24-1036
https://doi.org/10.1115/1.4065853
Published Online: July 16, 2024
View Articletitled, Performance of Borated Centrifugally Tensioned Metastable Fluid Detector Versus Ludlum 42-49B, Fuji NSN3 Detectors for Fission Energy Spectrum Neutron Detection With the Source Within Lead/Concrete Shielded Configurations
Open the PDF for Performance of Borated Centrifugally Tensioned Metastable Fluid Detector Versus Ludlum 42-49B, Fuji NSN3 Detectors for Fission Energy Spectrum Neutron Detection With the Source Within Lead/Concrete Shielded Configurations in another window
Topics: Concretes, Fluids, Neutrons, Sensors, Nuclear fission
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

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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 Articletitled, 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

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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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 Articletitled, Monitoring for Actinide Neutron Emissions From Spent Nuclear Fuel Under Extreme Gamma Fields Using Centrifugally Tensioned Metastable Fluid Detector Sensor Technology
Open the PDF for Monitoring for Actinide Neutron Emissions From Spent Nuclear Fuel Under Extreme Gamma Fields Using Centrifugally Tensioned Metastable Fluid Detector Sensor Technology in another window
Topics: Fluids, Neutrons, Sensors, Emissions, Photons, Spent nuclear fuels
Journal Articles

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

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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 Articletitled, 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

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

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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 Articletitled, 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

Dose Rate Assessment Around the PCFV Release Line During Severe Accident Conditions in Nuclear Power Plant Krsko

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Davor Grgic, Paulina Duckic, Vesna Bencik, Sinisa Sadek
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2024, 10(1): 011701.
Paper No: NERS-23-1019
https://doi.org/10.1115/1.4062797
Published Online: October 20, 2023
View Articletitled, Dose Rate Assessment Around the PCFV Release Line During Severe Accident Conditions in Nuclear Power Plant Krsko
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Topics: Accidents, Containment, Ducts, Nuclear power stations, Fluids
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
Open the PDF for 9 MV LINAC Photoneutron Interrogation of Uranium With Advanced Acoustically Tensioned Metastable Fluid Detectors in another window
Topics: Acoustics, Fluids, Neutrons, Photons, Sensors, Vacuum, Uranium, X-rays
Journal Articles

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

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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 Articletitled, 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

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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 Articletitled, 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

The Effect of Flow Channel Geometry on Thermomechanical Performance of Printed Circuit Heat Exchanger (PCHE)

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Witiwat Jiragoontansiri, Teerapat Woravisuttsarakul, Rinrada Sae-Pueng, Yanin Sukjai
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2023, 9(2): 021401.
Paper No: NERS-21-1156
https://doi.org/10.1115/1.4054546
Published Online: June 15, 2022
View Articletitled, The Effect of Flow Channel Geometry on Thermomechanical Performance of Printed Circuit Heat Exchanger (PCHE)
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Topics: Airfoils, Flow (Dynamics), Geometry, Stress, Heat exchangers, Heat transfer, Temperature, Fluids, Structural analysis
Journal Articles

Testing the Modified Subchannel tempa-sc Code in Comparison With Experiments and Other Computer Codes

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A. M. Baisov, A. N. Churkin, V. I. Deev, V. S. Kharitonov
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2022, 8(3): 031101.
Paper No: NERS-21-1101
https://doi.org/10.1115/1.4053049
Published Online: March 22, 2022
View Articletitled, Testing the Modified Subchannel tempa-sc Code in Comparison With Experiments and Other Computer Codes
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Topics: Coolants, Fluids, Fuel rods, Heat transfer, Momentum, Temperature, Water, Wall temperature, Flow (Dynamics), Testing
Journal Articles

Experiment and Codes to Support Safety Assessments for Sodium Fast Reactors (KASOLA, SOLTEC and KARIFA)

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Wolfgang Hering, Joachim Fuchs, Alexandru Onea, Sara Perez-Martin, Thomas Schaub
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2022, 8(1): 011324.
Paper No: NERS-21-1031
https://doi.org/10.1115/1.4052642
Published Online: December 7, 2021
View Articletitled, Experiment and Codes to Support Safety Assessments for Sodium Fast Reactors (KASOLA, SOLTEC and KARIFA)
Open the PDF for Experiment and Codes to Support Safety Assessments for Sodium Fast Reactors (KASOLA, SOLTEC and KARIFA) in another window
Topics: Flow (Dynamics), Safety, Sodium, Temperature, Test facilities, Liquid metals, Boiling, Computational fluid dynamics, Fluids, Instrumentation
Journal Articles

Actinide in Air (Rn-Progeny Rejected) Alpha Spectroscopy With Tensioned Metastable Fluid Detectors

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M. Hemesath, N. Boyle, B. Archambault, C. Troy Lorier, D. DiPrete, R. P. Taleyarkhan
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2022, 8(2): 022001.
Paper No: NERS-20-1188
https://doi.org/10.1115/1.4049729
Published Online: October 19, 2021
View Articletitled, Actinide in Air (Rn-Progeny Rejected) Alpha Spectroscopy With Tensioned Metastable Fluid Detectors
Open the PDF for Actinide in Air (Rn-Progeny Rejected) Alpha Spectroscopy With Tensioned Metastable Fluid Detectors in another window
Topics: Fluids, Sensors, Spectroscopy, Filters
Journal Articles

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

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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 Articletitled, Numerical Verifications on Heat Transfer to Supercritical Water Flowing Upward in a 4-m Long Bare Vertical Tube
Open the PDF for Numerical Verifications on Heat Transfer to Supercritical Water Flowing Upward in a 4-m Long Bare Vertical Tube in another window
Topics: Heat transfer, Turbulence, Water, Temperature, Computer simulation, Heat flux, Heat, Density, Flow (Dynamics), Viscosity
Journal Articles

Numerical Study of the Deposition of Radioactive Nuclide (Aerosol) in Pressurized Water Reactor Steam Generator

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Muhammad Aadil, Rab Nawaz, Ajmal Shah, Kamran Rasheed Qureshi
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2022, 8(2): 021801.
Paper No: NERS-20-1210
https://doi.org/10.1115/1.4051618
Published Online: October 19, 2021
View Articletitled, Numerical Study of the Deposition of Radioactive Nuclide (Aerosol) in Pressurized Water Reactor Steam Generator
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Topics: Aerosols, Boilers, Decontamination, Nuclides, Particulate matter, Pressurized water reactors, Turbulence, Computational fluid dynamics, Flow (Dynamics), Particle size
Journal Articles

Numerical Modeling and Experimental Validation of a Supercritical CO 2 -Lubricated Hydrodynamic Journal Bearing

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Nathan Colgan, Ken Cragin, Jeffrey Breedlove, Gregory Nellis, Mark Anderson
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2021, 7(3): 031802.
Paper No: NERS-20-1119
https://doi.org/10.1115/1.4049724
Published Online: May 26, 2021
View Articletitled, Numerical Modeling and Experimental Validation of a Supercritical CO 2 -Lubricated Hydrodynamic Journal Bearing
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Topics: Bearings, Pressure, Temperature, Computer simulation, Fluids
Journal Articles

Techno-Economic Study on Implementation of Inventory Control Requirements for a Nuclear-Powered Closed-Cycle Gas Turbine Power Plant

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Emmanuel O. Osigwe, Arnold Gad-Briggs, Mafel Obhuo, Pericles Pilidis
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2021, 7(3): 031301.
Paper No: NERS-19-1139
https://doi.org/10.1115/1.4048903
Published Online: February 19, 2021
View Articletitled, Techno-Economic Study on Implementation of Inventory Control Requirements for a Nuclear-Powered Closed-Cycle Gas Turbine Power Plant
Open the PDF for Techno-Economic Study on Implementation of Inventory Control Requirements for a Nuclear-Powered Closed-Cycle Gas Turbine Power Plant in another window
Topics: Closed-cycle gas turbines, Compressors, Control systems, Cycles, Fluids, Pressure, Storage tanks, Stress, Temperature, Valves
Journal Articles

Heat Transfer in Supercritical Fluids: A Review

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Kapil Bodkha, N. K. Maheshwari
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Review Articles
ASME J of Nuclear Rad Sci. July 2021, 7(3): 030802.
Paper No: NERS-20-1029
https://doi.org/10.1115/1.4048898
Published Online: February 19, 2021
View Articletitled, Heat Transfer in Supercritical Fluids: A Review
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Topics: Carbon dioxide, Fluids, Heat transfer, Supercritical fluids, Temperature, Water, Pressure, Heat flux