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Journal Articles

Joining of Zirconium Alloys to Nickel Bearing Alloys for In-Core Components

Michel Gaudet, Anne McLellan, Adrian Gerlich, Bruce Williams
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Technical Briefs
ASME J of Nuclear Rad Sci. July 2022, 8(3): 031106.
Paper No: NERS-21-1087
https://doi.org/10.1115/1.4054557
Published Online: May 17, 2022
View Article titled, Joining of Zirconium Alloys to Nickel Bearing Alloys for In-Core Components
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Topics: Alloys, Extruding, Friction welding, Zirconium alloys, Stainless steel, Bearings, Zirconium, Friction, Nickel, Supercritical water reactors
Journal Articles

Concept of a Small Modular SCWR With Horizontal Fuel Assemblies

Thomas Schulenberg, Ivan Otic
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Technical Briefs
ASME J of Nuclear Rad Sci. July 2022, 8(3): 031104.
Paper No: NERS-21-1074
https://doi.org/10.1115/1.4052191
Published Online: March 15, 2022
View Article titled, Concept of a Small Modular SCWR With Horizontal Fuel Assemblies
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Topics: Coolants, Design, Fuels, Heat, Supercritical water reactors, Water, Temperature, Light water reactors, Cladding systems (Building), Natural convection
Journal Articles

Deteriorated Heat Transfer Influence on the Stress–Strain State of Small Modular Reactors SCWR Fuel Bundles

Y. Dubyk, V. Filonov, Y. Filonova, O. Kovalenko
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2022, 8(3): 031105.
Paper No: NERS-21-1082
https://doi.org/10.1115/1.4052590
Published Online: March 15, 2022
View Article titled, Deteriorated Heat Transfer Influence on the Stress–Strain State of Small Modular Reactors SCWR Fuel Bundles
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Topics: Computational fluid dynamics, Heat transfer, Stress, Supercritical water reactors, Temperature, Fuels, Small modular reactors
Journal Articles

Guest Editorial by Gilles Rodriguez

Gilles Rodriguez
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Guest Editorial
ASME J of Nuclear Rad Sci. January 2022, 8(1): 010303.
Paper No: NERS-21-1137
https://doi.org/10.1115/1.4052719
Published Online: December 14, 2021
View Article titled, Guest Editorial by Gilles Rodriguez
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Topics: Carbon, Collaboration, Economics , Energy consumption, Heat, Hydrogen, Industrial capacity, Innovation, Manufacturing systems, Molten salt reactors
Journal Articles

GTAW Welded Inconel 625 Alloy Fuel Cladding for the Canadian SCWR: Microstructure and Mechanical Property Characterization

Cota-Sanchez German, Xiao Lin
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2021, 7(3): 031304.
Paper No: NERS-20-1053
https://doi.org/10.1115/1.4049278
Published Online: March 16, 2021
View Article titled, GTAW Welded Inconel 625 Alloy Fuel Cladding for the Canadian SCWR: Microstructure and Mechanical Property Characterization
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Topics: Heat, Welding, Cladding systems (Building), Fuels, Alloys, Supercritical water reactors, Mechanical properties, Gas tungsten arc welding, Welded joints
Journal Articles

European Research Program on Supercritical Water-Cooled Reactor

M. Kryková, T. Schulenberg, M. Arnoult Růžičková, A. Sáez-Maderuelo, I. Otic, S. Czifrus, L. Cizelj, G. L. Pavel
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2021, 7(2): 021301.
Paper No: NERS-20-1090
https://doi.org/10.1115/1.4048901
Published Online: November 16, 2020
View Article titled, European Research Program on Supercritical Water-Cooled Reactor
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Topics: Design, Safety, Small modular reactors, Supercritical water reactors, Water, Corrosion, Thermal hydraulics, Physics
Journal Articles

Evaluation of Friction-Factor Correlations at Supercritical Water Conditions in Support of the Canadian SCWR

A. Nava-Dominguez
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2020, 6(3): 031113.
Paper No: NERS-19-1082
https://doi.org/10.1115/1.4046783
Published Online: June 5, 2020
View Article titled, Evaluation of Friction-Factor Correlations at Supercritical Water Conditions in Support of the Canadian SCWR
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Topics: Flow (Dynamics), Friction, Pressure drop, Wire, Fuels, Water, Supercritical water reactors, Manufacturing, Pipes
Journal Articles

Special Section: Selected Papers From the Ninth International Symposium on Supercritical Water-Cooled Reactors

Laurence Leung, Ph.D., David Guzonas, Ph.D., Thomas Schulenberg, Ph.D.
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Guest Editorial
ASME J of Nuclear Rad Sci. July 2020, 6(3): 030301.
Paper No: NERS-20-1026
https://doi.org/10.1115/1.4046827
Published Online: June 5, 2020
View Article titled, Special Section: Selected Papers From the Ninth International Symposium on Supercritical Water-Cooled Reactors
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Topics: Supercritical water reactors, Water
Journal Articles

Analysis of Heat Transfer Characteristics of Canadian SCWR Fuel Assembly Concept

A. Nava Domínguez, Y. F. Rao, T. Beuthe
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2020, 6(3): 031114.
Paper No: NERS-19-1083
https://doi.org/10.1115/1.4046843
Published Online: June 5, 2020
View Article titled, Analysis of Heat Transfer Characteristics of Canadian SCWR Fuel Assembly Concept
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Topics: Cladding systems (Building), Coolants, Flow (Dynamics), Fuels, Heat losses, Heat transfer, Manufacturing, Supercritical water reactors, Temperature, Modeling
Journal Articles

About the Thermal Hydraulic Analysis Part of a Coupled Study on a Thorium-Fueled SCWR Concept

Attila Kiss, Béla Hegyesi, Patrik Richárd Ujváry, András Szabolcs Ványi, Gyula Csom
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2020, 6(3): 031108.
Paper No: NERS-19-1070
https://doi.org/10.1115/1.4046904
Published Online: June 5, 2020
View Article titled, About the Thermal Hydraulic Analysis Part of a Coupled Study on a Thorium-Fueled SCWR Concept
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Topics: Computational fluid dynamics, Flow (Dynamics), Fluids, Fuels, Manufacturing, Supercritical water reactors, Temperature, Fuel rods, Boundary-value problems, Wire
Journal Articles

Integration of Modeling Capabilities in CATHENA for Supercritical Water Reactors

T. Beuthe, A. Vasić, H. Zahlan, A. Nava Domínguez
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2020, 6(3): 031115.
Paper No: NERS-20-1002
https://doi.org/10.1115/1.4047288
Published Online: June 5, 2020
View Article titled, Integration of Modeling Capabilities in CATHENA for Supercritical Water Reactors
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Topics: Heat transfer, Modeling, Pressure, Supercritical water reactors, Temperature, Simulation, Accidents, Testing, Water, Transients (Dynamics)
Journal Articles

Research on Improved Simplified SCWR Assembly and Core Design

Yao Lei, Xia Bangyang, Lu Di, Wang Lianjie
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2020, 6(3): 031106.
Paper No: NERS-19-1063
https://doi.org/10.1115/1.4046261
Published Online: June 5, 2020
View Article titled, Research on Improved Simplified SCWR Assembly and Core Design
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Topics: Coolants, Design, Fuels, Manufacturing, Supercritical water reactors, Water, Flow (Dynamics), Temperature
Journal Articles

Fast Neutron Irradiation Optimization of Thorium-Fueled SCWR Reactor Pressure Vessel

Petra Pónya, Gyula Csom, Sándor Fehér
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2020, 6(3): 031110.
Paper No: NERS-19-1079
https://doi.org/10.1115/1.4046354
Published Online: June 5, 2020
View Article titled, Fast Neutron Irradiation Optimization of Thorium-Fueled SCWR Reactor Pressure Vessel
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Topics: Coolants, Flow (Dynamics), Irradiation (Radiation exposure), Neutron flux, Neutrons, Reactor vessels, Supercritical water reactors, Design, Fuels, Temperature
Journal Articles

Study on Calculation Difference of the SCWR Core Steady-State Analysis Code

Lianjie Wang, Lei Yao, Ping Yang, Di Lu, Wenbo Zhao
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2020, 6(3): 031103.
Paper No: NERS-19-1054
https://doi.org/10.1115/1.4044408
Published Online: June 5, 2020
View Article titled, Study on Calculation Difference of the SCWR Core Steady-State Analysis Code
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Topics: Density, Feedback, Steady state, Supercritical water reactors, Thermal hydraulics, Water, Flow (Dynamics)
Journal Articles

Analysis of Shutdown System Effectiveness in the Canadian Super Critical Water Reactor Using Coupled Thermal Hydraulics and Three-Dimensional Neutron Kinetics

David William Hummel, David Raymond Novog
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2019, 5(4): 041403.
Paper No: NERS-18-1008
https://doi.org/10.1115/1.4042597
Published Online: September 3, 2019
View Article titled, Analysis of Shutdown System Effectiveness in the Canadian Super Critical Water Reactor Using Coupled Thermal Hydraulics and Three-Dimensional Neutron Kinetics
Open the PDF for Analysis of Shutdown System Effectiveness in the Canadian Super Critical Water Reactor Using Coupled Thermal Hydraulics and Three-Dimensional Neutron Kinetics in another window
Topics: Blades, Coolants, Flow (Dynamics), Fuels, Neutrons, Supercritical water reactors, Thermal hydraulics, Transients (Dynamics), Water, Delays
Journal Articles

Performance of Aluminide and Cr-Modified Aluminide Pack Cementation-Coated Stainless Steel 304 in Supercritical Water at 700 °C

Nick Tepylo, Xiao Huang, Shengli Jiang, Sami Penttilä
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2019, 5(1): 011014.
Paper No: NERS-18-1016
https://doi.org/10.1115/1.4040889
Published Online: January 24, 2019
View Article titled, Performance of Aluminide and Cr-Modified Aluminide Pack Cementation-Coated Stainless Steel 304 in Supercritical Water at 700 °C
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Topics: Coating processes, Coatings, Oxidation, Spallation (Nuclear physics), Stainless steel, Supercritical water reactors, Water, Weight (Mass), X-ray diffraction, Alloys
Journal Articles

Coupled Three-Dimensional Neutronics and Thermal-Hydraulics Analysis for SCWR Core Typical Transients

Wang Lianjie, Lu Di, Zhao Wenbo
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2019, 5(1): 011010.
Paper No: NERS-18-1047
https://doi.org/10.1115/1.4041693
Published Online: January 24, 2019
View Article titled, Coupled Three-Dimensional Neutronics and Thermal-Hydraulics Analysis for SCWR Core Typical Transients
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Topics: Safety, Supercritical water reactors, Thermal hydraulics, Transient analysis, Transients (Dynamics), Accidents, Fuels, Temperature, Water, Density
Journal Articles

Irradiation Issues and Material Selection for Canadian SCWR Components

L. Walters, M. Wright, D. Guzonas
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2018, 4(3): 031005.
Paper No: NERS-17-1045
https://doi.org/10.1115/1.4038367
Published Online: May 16, 2018
View Article titled, Irradiation Issues and Material Selection for Canadian SCWR Components
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Topics: Alloys, Irradiation (Radiation exposure), Supercritical water reactors, Temperature, Neutrons, Fuels, Water, Stainless steel, Helium
Journal Articles

Optimization of the Canadian SCWR Core Using Coupled Three-Dimensional Reactor Physics and Thermal-Hydraulics Calculations

F. Salaun, D. R. Novog
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2018, 4(2): 021003.
Paper No: NERS-17-1010
https://doi.org/10.1115/1.4038557
Published Online: March 5, 2018
View Article titled, Optimization of the Canadian SCWR Core Using Coupled Three-Dimensional Reactor Physics and Thermal-Hydraulics Calculations
Open the PDF for Optimization of the Canadian SCWR Core Using Coupled Three-Dimensional Reactor Physics and Thermal-Hydraulics Calculations in another window
Topics: Blades, Cycles, Design, Fuels, Optimization, Physics, Supercritical water reactors, Temperature, Thermal hydraulics, Coolants
Journal Articles

Special Issue: Selected Papers from the 8th International Symposium on Supercritical Water-Cooled Reactors

Thomas Schulenberg
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Guest Editorial
ASME J of Nuclear Rad Sci. January 2018, 4(1): 010301.
Paper No: NERS-17-1070
https://doi.org/10.1115/1.4037556
Published Online: December 4, 2017
View Article titled, Special Issue: Selected Papers from the 8th International Symposium on Supercritical Water-Cooled Reactors
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Topics: Supercritical water reactors, Water, Nuclear engineering, China