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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

ASME J of Nuclear Rad Sci. July 2022, 8(3): 031106.

Paper No: NERS-21-1087

DOI: https://doi.org/10.1115/1.4054557

Published Online: May 17, 2022

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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

ASME J of Nuclear Rad Sci. July 2022, 8(3): 031104.

Paper No: NERS-21-1074

DOI: https://doi.org/10.1115/1.4052191

Published Online: March 15, 2022

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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

ASME J of Nuclear Rad Sci. July 2022, 8(3): 031105.

Paper No: NERS-21-1082

DOI: https://doi.org/10.1115/1.4052590

Published Online: March 15, 2022

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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

ASME J of Nuclear Rad Sci. January 2022, 8(1): 010303.

Paper No: NERS-21-1137

DOI: https://doi.org/10.1115/1.4052719

Published Online: December 14, 2021

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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

ASME J of Nuclear Rad Sci. July 2021, 7(3): 031304.

Paper No: NERS-20-1053

DOI: https://doi.org/10.1115/1.4049278

Published Online: March 16, 2021

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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

ASME J of Nuclear Rad Sci. April 2021, 7(2): 021301.

Paper No: NERS-20-1090

DOI: https://doi.org/10.1115/1.4048901

Published Online: November 16, 2020

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Topics: Design, Safety, Small modular reactors, Supercritical water reactors, Water, Corrosion, Thermal hydraulics, Physics

Journal Articles

Research on Improved Simplified SCWR Assembly and Core Design

Yao Lei, Xia Bangyang, Lu Di, Wang Lianjie

ASME J of Nuclear Rad Sci. July 2020, 6(3): 031106.

Paper No: NERS-19-1063

DOI: https://doi.org/10.1115/1.4046261

Published Online: June 5, 2020

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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

ASME J of Nuclear Rad Sci. July 2020, 6(3): 031110.

Paper No: NERS-19-1079

DOI: https://doi.org/10.1115/1.4046354

Published Online: June 5, 2020

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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

ASME J of Nuclear Rad Sci. July 2020, 6(3): 031103.

Paper No: NERS-19-1054

DOI: https://doi.org/10.1115/1.4044408

Published Online: June 5, 2020

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Topics: Density, Feedback, Steady state, Supercritical water reactors, Thermal hydraulics, Water, Flow (Dynamics)

Journal Articles

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

A. Nava-Dominguez

ASME J of Nuclear Rad Sci. July 2020, 6(3): 031113.

Paper No: NERS-19-1082

DOI: https://doi.org/10.1115/1.4046783

Published Online: June 5, 2020

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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.

ASME J of Nuclear Rad Sci. July 2020, 6(3): 030301.

Paper No: NERS-20-1026

DOI: https://doi.org/10.1115/1.4046827

Published Online: June 5, 2020

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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

ASME J of Nuclear Rad Sci. July 2020, 6(3): 031114.

Paper No: NERS-19-1083

DOI: https://doi.org/10.1115/1.4046843

Published Online: June 5, 2020

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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

ASME J of Nuclear Rad Sci. July 2020, 6(3): 031108.

Paper No: NERS-19-1070

DOI: https://doi.org/10.1115/1.4046904

Published Online: June 5, 2020

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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

ASME J of Nuclear Rad Sci. July 2020, 6(3): 031115.

Paper No: NERS-20-1002

DOI: https://doi.org/10.1115/1.4047288

Published Online: June 5, 2020

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Topics: Heat transfer, Modeling, Pressure, Supercritical water reactors, Temperature, Simulation, Accidents, Testing, Water, Transients (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

ASME J of Nuclear Rad Sci. October 2019, 5(4): 041403.

Paper No: NERS-18-1008

DOI: https://doi.org/10.1115/1.4042597

Published Online: September 3, 2019

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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

ASME J of Nuclear Rad Sci. January 2019, 5(1): 011014.

Paper No: NERS-18-1016

DOI: https://doi.org/10.1115/1.4040889

Published Online: January 24, 2019

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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

ASME J of Nuclear Rad Sci. January 2019, 5(1): 011010.

Paper No: NERS-18-1047

DOI: https://doi.org/10.1115/1.4041693

Published Online: January 24, 2019

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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

ASME J of Nuclear Rad Sci. July 2018, 4(3): 031005.

Paper No: NERS-17-1045

DOI: https://doi.org/10.1115/1.4038367

Published Online: May 16, 2018

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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

ASME J of Nuclear Rad Sci. April 2018, 4(2): 021003.

Paper No: NERS-17-1010

DOI: https://doi.org/10.1115/1.4038557

Published Online: March 5, 2018

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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

ASME J of Nuclear Rad Sci. January 2018, 4(1): 010301.

Paper No: NERS-17-1070

DOI: https://doi.org/10.1115/1.4037556

Published Online: December 4, 2017

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Topics: Supercritical water reactors, Water, Nuclear engineering, China

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Journal citation

NARROW

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

Concept of a Small Modular SCWR With Horizontal Fuel Assemblies

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

Guest Editorial by Gilles Rodriguez

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

European Research Program on Supercritical Water-Cooled Reactor

Research on Improved Simplified SCWR Assembly and Core Design

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

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

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

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

Analysis of Heat Transfer Characteristics of Canadian SCWR Fuel Assembly Concept

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

Integration of Modeling Capabilities in CATHENA for Supercritical Water Reactors

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

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

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

Irradiation Issues and Material Selection for Canadian SCWR Components

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

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

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