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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
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2023, 9(3): 031401.
Paper No: NERS-21-1158
DOI: 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
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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
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2021, 7(2): 021603.
Paper No: NERS-20-1148
DOI: https://doi.org/10.1115/1.4048847
Published Online: November 16, 2020
View Article titled, Induction Annealing of Austenitic Spring Steels for Nuclear Reactors
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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
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2021, 7(2): 021802.
Paper No: NERS-20-1093
DOI: 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
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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
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
DOI: 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

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

Attila Kiss, Bence Mervay
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2020, 6(3): 031107.
Paper No: NERS-19-1069
DOI: 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
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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
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
DOI: 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

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
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2019, 5(2): 021001.
Paper No: NERS-17-1280
DOI: 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
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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
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2018, 4(3): 031015.
Paper No: NERS-17-1262
DOI: 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
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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
Journal: Journal of Nuclear Engineering and Radiation Science
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2018, 4(1): 011008.
Paper No: NERS-17-1027
DOI: 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
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Topics: Computational fluid dynamics, Flow (Dynamics), Fuel rods, Heat transfer, Pressure, Simulation, Turbulence, Water, Wire, Temperature