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Journal Articles

Eddy Current Flow Meter Measurements in Liquid Sodium at High Temperatures

Nico Krauter, Alexandru Aurelian Onea, Gunter Gerbeth, Sven Eckert

Publisher: ASME

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 Article titled, Eddy Current Flow Meter Measurements in Liquid Sodium at High Temperatures

Topics: Eddies (Fluid dynamics), Flow (Dynamics), Flowmeters, High temperature, Sensors, Sodium, Temperature, Wire, Eddy currents (Electricity), Liquid metals

Journal Articles

Investigation on Applicability of Subchannel Analysis Code ASFRE to Thermal Hydraulics Analysis in Fuel Assembly With Inner Duct Structure of Sodium Cooled Fast Reactor

Norihiro Kikuchi, Yasutomo Imai, Ryuji Yoshikawa, Norihiro Doda, Masaaki Tanaka

Publisher: ASME

ASME J of Nuclear Rad Sci. July 2023, 9(3): 031401.

Paper No: NERS-21-1158

https://doi.org/10.1115/1.4056463

Published Online: February 8, 2023

View Article titled, Investigation on Applicability of Subchannel Analysis Code ASFRE to Thermal Hydraulics Analysis in Fuel Assembly With Inner Duct Structure of Sodium Cooled Fast Reactor

Topics: Ducts, Flow (Dynamics), Fuels, Manufacturing, Sodium fast reactors, Temperature, Temperature distribution, Thermal hydraulics, Wire, Fuel rods

Journal Articles

Induction Annealing of Austenitic Spring Steels for Nuclear Reactors

Jiri Hajek, David Rot, Jana Cubrova, Jakub Jirinec

Publisher: ASME

ASME J of Nuclear Rad Sci. April 2021, 7(2): 021603.

Paper No: NERS-20-1148

https://doi.org/10.1115/1.4048847

Published Online: November 16, 2020

View Article titled, Induction Annealing of Austenitic Spring Steels for Nuclear Reactors

Topics: Annealing, Electromagnetic induction, Steel, Temperature, Wire, Heating, Inductors

Journal Articles

On Debris-Fretting Impact—The Study of Oxide and Chromium Layer Application

Marcin Kopeć, Ondřej Pašta, Martina Malá, Patricie Halodová, Ladislav Cvrček, Jakub Krejčí

Publisher: ASME

ASME J of Nuclear Rad Sci. April 2021, 7(2): 021802.

Paper No: NERS-20-1093

https://doi.org/10.1115/1.4048239

Published Online: November 16, 2020

View Article titled, On Debris-Fretting Impact—The Study of Oxide and Chromium Layer Application

Topics: Cladding systems (Building), Coatings, Fuels, Testing, Wear, Wire, Zirconium, Failure, X-rays, Focused ion beams

Journal Articles

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

A. Nava-Dominguez

Publisher: ASME

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

Topics: Flow (Dynamics), Friction, Pressure drop, Wire, Fuels, Water, Supercritical water reactors, Manufacturing, Pipes

Journal Articles

Further Details of a Numerical Analysis on the Thermal Hydraulic Effect of Wrapped Wire Spacers in Fuel Bundle

Attila Kiss, Bence Mervay

Publisher: ASME

ASME J of Nuclear Rad Sci. July 2020, 6(3): 031107.

Paper No: NERS-19-1069

https://doi.org/10.1115/1.4046842

Published Online: June 5, 2020

View Article titled, Further Details of a Numerical Analysis on the Thermal Hydraulic Effect of Wrapped Wire Spacers in Fuel Bundle

Topics: Flow (Dynamics), Fuel rods, Geometry, Wire, Wall temperature, Fuels, Corners (Structural elements), Temperature

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

Publisher: ASME

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

Topics: Computational fluid dynamics, Flow (Dynamics), Fluids, Fuels, Manufacturing, Supercritical water reactors, Temperature, Fuel rods, Boundary-value problems, Wire

Journal Articles

Subchannel Analysis of Thermal-Hydraulics in a Fuel Assembly With Inner Duct Structure of a Sodium-Cooled Fast Reactor

Norihiro Kikuchi, Yasutomo Imai, Ryuji Yoshikawa, Norihiro Doda, Masaaki Tanaka, Hiroyuki Ohshima

Publisher: ASME

ASME J of Nuclear Rad Sci. April 2019, 5(2): 021001.

Paper No: NERS-17-1280

https://doi.org/10.1115/1.4042191

Published Online: March 15, 2019

View Article titled, Subchannel Analysis of Thermal-Hydraulics in a Fuel Assembly With Inner Duct Structure of a Sodium-Cooled Fast Reactor

Topics: Ducts, Flow (Dynamics), Fuels, Manufacturing, Sodium, Temperature distribution, Temperature, Sodium fast reactors, Wire, Thermal hydraulics

Journal Articles

A Numerical Analysis Method of Impurity Precipitation on Mesh Wire of Cold Trap in Fast Breeder Reactor

Akinori Tamura, Shiro Takahashi, Hiroyuki Nakata, Akio Takota

Publisher: ASME

ASME J of Nuclear Rad Sci. July 2018, 4(3): 031015.

Paper No: NERS-17-1262

https://doi.org/10.1115/1.4039037

Published Online: May 16, 2018

View Article titled, A Numerical Analysis Method of Impurity Precipitation on Mesh Wire of Cold Trap in Fast Breeder Reactor

Topics: Flow (Dynamics), Numerical analysis, Precipitation, Reynolds number, Simulation, Wire, Breeder reactors, Computer simulation, Pressure, Sodium

Journal Articles

Computational Fluid Dynamic Simulations of Heat Transfer From a 2 × 2 Wire-Wrapped Fuel Rod Bundle to Supercritical Pressure Water

Krishna Podila, Yanfei Rao

Publisher: ASME

ASME J of Nuclear Rad Sci. January 2018, 4(1): 011008.

Paper No: NERS-17-1027

https://doi.org/10.1115/1.4037747

Published Online: December 4, 2017

View Article titled, Computational Fluid Dynamic Simulations of Heat Transfer From a 2 × 2 Wire-Wrapped Fuel Rod Bundle to Supercritical Pressure Water

Topics: Computational fluid dynamics, Flow (Dynamics), Fuel rods, Heat transfer, Pressure, Simulation, Turbulence, Water, Wire, Temperature

Journal citation

NARROW

Eddy Current Flow Meter Measurements in Liquid Sodium at High Temperatures

Investigation on Applicability of Subchannel Analysis Code ASFRE to Thermal Hydraulics Analysis in Fuel Assembly With Inner Duct Structure of Sodium Cooled Fast Reactor

Induction Annealing of Austenitic Spring Steels for Nuclear Reactors

On Debris-Fretting Impact—The Study of Oxide and Chromium Layer Application

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

Further Details of a Numerical Analysis on the Thermal Hydraulic Effect of Wrapped Wire Spacers in Fuel Bundle

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

Subchannel Analysis of Thermal-Hydraulics in a Fuel Assembly With Inner Duct Structure of a Sodium-Cooled Fast Reactor

A Numerical Analysis Method of Impurity Precipitation on Mesh Wire of Cold Trap in Fast Breeder Reactor

Computational Fluid Dynamic Simulations of Heat Transfer From a 2 × 2 Wire-Wrapped Fuel Rod Bundle to Supercritical Pressure Water

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