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Journal Articles

Progress on a Preconceptual Supercritical Water-Cooled Small Modular Reactor

Open Access
A. Nava Dominguez, Xianmin Huang, Michel Gaudet, Kittima Khumsa-Ang, Alberto D'Ansi Mendoza España, Jimmy Chow, Danila Roubtsov, Hygreeva Namburi
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2025, 11(3): 031301.
Paper No: NERS-24-1027
https://doi.org/10.1115/1.4068326
Published Online: May 8, 2025
View Articletitled, Progress on a Preconceptual Supercritical Water-Cooled Small Modular Reactor
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Topics: Cladding systems (Building), Coolants, Design, Fuels, Loss of coolant accidents, Safety, Temperature, Water, Flow (Dynamics), Small modular reactors
Journal Articles

Kinetic Study of Magnetite Precipitation Using a High-Temperature Flow-Through Loop: Experimental Apparatus and Testing Procedure

Available to Purchase
V. Oancherd, S. Weerakul, C. Drost, O. Palazhchenko, C. Kongvarhodom
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Technical Briefs
ASME J of Nuclear Rad Sci. July 2025, 11(3): 034504.
Paper No: NERS-24-1107
https://doi.org/10.1115/1.4068168
Published Online: April 16, 2025
View Articletitled, Kinetic Study of Magnetite Precipitation Using a High-Temperature Flow-Through Loop: Experimental Apparatus and Testing Procedure
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Topics: Flow (Dynamics), High temperature, Iron, Magnetite, Precipitation, Temperature
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

An Estimation Method for Bias Error of Measurements by Utilizing Process Data, An Incidence Matrix and a Reference Instrument for Data Validation and Reconciliation: Extension to the Energy Balance Relation

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Akinori Tamura, Yuki Hidaka, Haruhiko Ikeda, Norikazu Hamaura
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2025, 11(2): 021101.
Paper No: NERS-24-1037
https://doi.org/10.1115/1.4066344
Published Online: October 22, 2024
View Articletitled, An Estimation Method for Bias Error of Measurements by Utilizing Process Data, An Incidence Matrix and a Reference Instrument for Data Validation and Reconciliation: Extension to the Energy Balance Relation
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Topics: Energy budget (Physics), Errors, Flow (Dynamics), Instrumentation, Temperature measurement, Measurement uncertainty, Uncertainty, Sensors, Temperature, Nuclear power stations
Journal Articles

Estimation of Turbulent Mixing Factor and Study of Turbulent Flow Structures in Pressurized Water Reactor Sub Channel by Direct Numerical Simulation

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R. K. Singh, Deb Mukhopadhyay, D. Khakhar, J. B. Joshi
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2025, 11(2): 021001.
Paper No: NERS-24-1004
https://doi.org/10.1115/1.4066001
Published Online: October 8, 2024
View Articletitled, Estimation of Turbulent Mixing Factor and Study of Turbulent Flow Structures in Pressurized Water Reactor Sub Channel by Direct Numerical Simulation
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Topics: Computer simulation, Flow (Dynamics), Turbulence, Momentum, Pressurized water reactors
Journal Articles

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

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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 Articletitled, 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

Fabrication Aspects and Performance Characterization of α-Al 2 O 3 /AlPO 4 Based Sandwich Configuration Flow Channel Inserts and Coatings for High Temperature Liquid Metal Applications

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Abhishek Saraswat, Rajendraprasad Bhattacharyay, Paritosh Chaudhuri, Sateesh Gedupudi
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2024, 10(3): 030902.
Paper No: NERS-23-1007
https://doi.org/10.1115/1.4062646
Published Online: March 8, 2024
View Articletitled, Fabrication Aspects and Performance Characterization of α-Al 2 O 3 /AlPO 4 Based Sandwich Configuration Flow Channel Inserts and Coatings for High Temperature Liquid Metal Applications
Open the PDF for Fabrication Aspects and Performance Characterization of α-Al 2 O 3 /AlPO 4 Based Sandwich Configuration Flow Channel Inserts and Coatings for High Temperature Liquid Metal Applications in another window
Topics: Coatings, Engineering prototypes, Flow (Dynamics), High temperature, Insulation, Liquid metals, Magnetohydrodynamics, Manufacturing, Pressure, Welding
Journal Articles

Development and Testing of a System Thermal-Hydraulics Model for a 50-MW el -Class Pressurized Water Reactor–Small Modular Reactor

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Shujun Wang, Xianmin Huang, Yanfei Rao, 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): 021402.
Paper No: NERS-23-1086
https://doi.org/10.1115/1.4063240
Published Online: January 29, 2024
View Articletitled, Development and Testing of a System Thermal-Hydraulics Model for a 50-MW el -Class Pressurized Water Reactor–Small Modular Reactor
Open the PDF for Development and Testing of a System Thermal-Hydraulics Model for a 50-MW el -Class Pressurized Water Reactor–Small Modular Reactor in another window
Topics: Boilers, Design, Flow (Dynamics), Pressure, Pressurized water reactors, Small modular reactors, Temperature, Thermal hydraulics, Oscillations, Junctions
Journal Articles

Depletion Calculations for an Integral Small Molten Salt Reactor With Serpent

Open Access
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 Articletitled, 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

Uncertainty and Sensitivity Evaluation of the QUENCH-02 Experiment Simulation Using the ASYST Code

Available to Purchase
Siniša Šadek, Renato Pavlinac, Karlo Ivanjko, Davor Grgić
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2024, 10(1): 011301.
Paper No: NERS-23-1016
https://doi.org/10.1115/1.4062799
Published Online: October 20, 2023
View Articletitled, Uncertainty and Sensitivity Evaluation of the QUENCH-02 Experiment Simulation Using the ASYST Code
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Topics: Cladding systems (Building), Electricity (Physics), Flow (Dynamics), Hydrogen, Oxidation, Steam, Temperature, Uncertainty, Water, Boundary-value problems
Journal Articles

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

Available to Purchase
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 Articletitled, 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

Eddy Current Flow Meter Measurements in Liquid Sodium at High Temperatures

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Nico Krauter, Alexandru Aurelian Onea, Gunter Gerbeth, Sven Eckert
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2023, 9(4): 041301.
Paper No: NERS-22-1185
https://doi.org/10.1115/1.4062239
Published Online: September 15, 2023
View Articletitled, Eddy Current Flow Meter Measurements in Liquid Sodium at High Temperatures
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Topics: Eddies (Fluid dynamics), Flow (Dynamics), Flowmeters, High temperature, Sensors, Sodium, Temperature, Wire, Eddy currents (Electricity), Liquid metals
Journal Articles

System Thermal-Hydraulics Model for Fluoride Salt-Cooled Reactor Based on Small Modular Advanced High Temperature Reactor (SmAHTR) Design Concept

Available to Purchase
Shujun Wang, Xianmin Huang, Blair P. Bromley
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2023, 9(4): 041302.
Paper No: NERS-23-1011
https://doi.org/10.1115/1.4062500
Published Online: September 15, 2023
View Articletitled, System Thermal-Hydraulics Model for Fluoride Salt-Cooled Reactor Based on Small Modular Advanced High Temperature Reactor (SmAHTR) Design Concept
Open the PDF for System Thermal-Hydraulics Model for Fluoride Salt-Cooled Reactor Based on Small Modular Advanced High Temperature Reactor (SmAHTR) Design Concept in another window
Topics: Coolants, Cycles, Design, Flow (Dynamics), Fuels, High temperature, Modeling, Temperature, Thermal hydraulics, Steady state
Journal Articles

An Estimation Method for Bias Error of Measurements by Utilizing Process Data, An Incidence Matrix and a Reference Instrument for Data Validation and Reconciliation

Available to Purchase
Akinori Tamura, Yuki Hidaka, Haruhiko Ikeda, Norikazu Hamaura
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2023, 9(4): 041802.
Paper No: NERS-23-1050
https://doi.org/10.1115/1.4062865
Published Online: September 15, 2023
View Articletitled, An Estimation Method for Bias Error of Measurements by Utilizing Process Data, An Incidence Matrix and a Reference Instrument for Data Validation and Reconciliation
Open the PDF for An Estimation Method for Bias Error of Measurements by Utilizing Process Data, An Incidence Matrix and a Reference Instrument for Data Validation and Reconciliation in another window
Topics: Errors, Flow (Dynamics), Instrumentation, Measurement uncertainty, Uncertainty, Nuclear power stations, Sensors, Pipes
Journal Articles

Neutronic and Thermal-Fluidic Analyses for an Additive Manufactured Reactor With SiC Matrix and TRISO Particle Fuel

Available to Purchase
Wenbin Han, Jian Deng, Qi Lu, Chong Chen, Youyou Xu, Tao Zhang, Shanfang Huang
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2023, 9(4): 041104.
Paper No: NERS-22-1145
https://doi.org/10.1115/1.4062119
Published Online: April 17, 2023
View Articletitled, Neutronic and Thermal-Fluidic Analyses for an Additive Manufactured Reactor With SiC Matrix and TRISO Particle Fuel
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Topics: Additive manufacturing, Computational fluid dynamics, Design, Fuels, Particulate matter, Temperature, Coolants, Neutrons, Heat transfer, Computer software
Journal Articles

Development of a Passive Reactor Shutdown Device to Prevent Core Disruptive Accidents in Fast Reactors: A Study on Device Specifications

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Koji Morita, Wei Liu, Tatsumi Arima, Yuji Arita, Isamu Sato, Haruaki Matsuura, Yoshihiro Sekio, Hiroshi Sagara, Masatoshi Kawashima
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2023, 9(4): 041102.
Paper No: NERS-22-1136
https://doi.org/10.1115/1.4056854
Published Online: March 14, 2023
View Articletitled, Development of a Passive Reactor Shutdown Device to Prevent Core Disruptive Accidents in Fast Reactors: A Study on Device Specifications
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Topics: Coolants, Flow (Dynamics), Fuels, Sodium, Temperature, Accidents, Transients (Dynamics), Pins (Engineering)
Journal Articles

Development of a Passive Reactor Shutdown Device to Prevent Core Disruptive Accidents in Fast Reactors: A Preliminary Study

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Koji Morita, Wei Liu, Tatsumi Arima, Yuji Arita, Isamu Sato, Haruaki Matsuura, Yoshihiro Sekio, Hiroshi Sagara, Masatoshi Kawashima
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2023, 9(2): 021301.
Paper No: NERS-21-1161
https://doi.org/10.1115/1.4056834
Published Online: March 2, 2023
View Articletitled, Development of a Passive Reactor Shutdown Device to Prevent Core Disruptive Accidents in Fast Reactors: A Preliminary Study
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Topics: Accidents, Coolants, Fuels, Temperature, Fast neutron reactors, Flow (Dynamics), Pins (Engineering), Transients (Dynamics)
Journal Articles

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

Available to Purchase
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
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Topics: Fluids, Heat transfer, Particulate matter, Simulation, Temperature, Flow (Dynamics), Design, Fuels, Safety, Natural convection