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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

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Norihiro Kikuchi, Yasutomo Imai, Ryuji Yoshikawa, Norihiro Doda, Masaaki Tanaka
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
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 Articletitled, 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

Prediction Method for Condensation Heat Transfer in the Presence of Noncondensable Gas for Computational Fluid Dynamics Applications

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Michio Murase, Yoichi Utanohara, Akio Tomiyama
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2022, 8(3): 031404.
Paper No: NERS-21-1097
https://doi.org/10.1115/1.4053051
Published Online: May 26, 2022
View Articletitled, Prediction Method for Condensation Heat Transfer in the Presence of Noncondensable Gas for Computational Fluid Dynamics Applications
Open the PDF for Prediction Method for Condensation Heat Transfer in the Presence of Noncondensable Gas for Computational Fluid Dynamics Applications in another window
Topics: Condensation, Heat transfer, Steam, Temperature, Temperature distribution, Computational fluid dynamics, Mass transfer, Flat plates
Journal Articles

Development and Processing of Thermal-Hydraulic Model for GFR 2400 Fast Reactor Design and NESTLE Coupled Transient Code

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Filip Osuský, Branislav Vrban, Štefan Čerba, Jakub Lüley, Vladimír Nečas
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2022, 8(4): 041401.
Paper No: NERS-21-1012
https://doi.org/10.1115/1.4051515
Published Online: March 22, 2022
View Articletitled, Development and Processing of Thermal-Hydraulic Model for GFR 2400 Fast Reactor Design and NESTLE Coupled Transient Code
Open the PDF for Development and Processing of Thermal-Hydraulic Model for GFR 2400 Fast Reactor Design and NESTLE Coupled Transient Code in another window
Topics: Coolants, Design, Fast neutron reactors, Fuels, Heat, Temperature, Transients (Dynamics), Temperature distribution, Simulation, Cladding systems (Building)
Journal Articles

Testing the Modified Subchannel tempa-sc Code in Comparison With Experiments and Other Computer Codes

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A. M. Baisov, A. N. Churkin, V. I. Deev, V. S. Kharitonov
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2022, 8(3): 031101.
Paper No: NERS-21-1101
https://doi.org/10.1115/1.4053049
Published Online: March 22, 2022
View Articletitled, Testing the Modified Subchannel tempa-sc Code in Comparison With Experiments and Other Computer Codes
Open the PDF for Testing the Modified Subchannel tempa-sc Code in Comparison With Experiments and Other Computer Codes in another window
Topics: Coolants, Fluids, Fuel rods, Heat transfer, Momentum, Temperature, Water, Wall temperature, Flow (Dynamics), Testing
Journal Articles

Neutronic and Thermal-Mechanical Coupling Schemes for Heat Pipe-Cooled Reactor Designs

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Yugao Ma, Minyun Liu, Biheng Xie, Wenbin Han, Xiaoming Chai, Shanfang Huang, Hongxing Yu
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2022, 8(2): 021303.
Paper No: NERS-20-1207
https://doi.org/10.1115/1.4051612
Published Online: October 19, 2021
View Articletitled, Neutronic and Thermal-Mechanical Coupling Schemes for Heat Pipe-Cooled Reactor Designs
Open the PDF for Neutronic and Thermal-Mechanical Coupling Schemes for Heat Pipe-Cooled Reactor Designs in another window
Topics: Design, Displacement, Fuels, Geometry, Heat, Heat pipes, Molten salt reactors, Nuclear fission, Pipes, Temperature
Journal Articles

Improved Computational Fluid Dynamics Framework for Reactor Core Baffle Swelling Assessment

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Yuliia Filonova, Yaroslav Dubyk, Vladislav Filonov, Vadym Kondratjuk
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2021, 7(1): 011404.
Paper No: NERS-20-1009
https://doi.org/10.1115/1.4047495
Published Online: October 5, 2020
View Articletitled, Improved Computational Fluid Dynamics Framework for Reactor Core Baffle Swelling Assessment
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Topics: Boundary-value problems, Computational fluid dynamics, Coolants, Flow (Dynamics), Geometry, Temperature, Cooling, Temperature distribution, Metals
Journal Articles

Computational Fluid Dynamics Thermal Analysis of ITER Pressure Suppression Tanks

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Lorenzo Basili, Rosa Lo Frano, Marco Olcese, Igor Sekachev, Donato Aquaro
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2021, 7(1): 012301.
Paper No: NERS-19-1156
https://doi.org/10.1115/1.4048007
Published Online: October 5, 2020
View Articletitled, Computational Fluid Dynamics Thermal Analysis of ITER Pressure Suppression Tanks
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Topics: Accidents, Computational fluid dynamics, Design, Flanges, Insulation, Pressure, Stress, Temperature, Temperature gradient, Thermal analysis
Journal Articles

Experimental Validation of ANSYS CFX for Transient Flows With Heat Transfer in a Tubular Heat Exchanger

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Angel Papukchiev
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2020, 6(2): 021104.
Paper No: NERS-19-1029
https://doi.org/10.1115/1.4045074
Published Online: January 29, 2020
View Articletitled, Experimental Validation of ANSYS CFX for Transient Flows With Heat Transfer in a Tubular Heat Exchanger
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Topics: Flow (Dynamics), Fluids, Heat exchangers, Heat transfer, Modeling, Simulation, Temperature, Transients (Dynamics), Turbulence, Computational fluid dynamics
Journal Articles

Experimental Investigation on Flash Evaporation Related to Pipe Leakage

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Benan Cai, Qi Zhang, Yu Weng, Hongfang Gu, Haijun Wang
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2020, 6(1): 011401.
Paper No: NERS-17-1237
https://doi.org/10.1115/1.4045125
Published Online: November 29, 2019
View Articletitled, Experimental Investigation on Flash Evaporation Related to Pipe Leakage
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Topics: Evaporation, Flow (Dynamics), High temperature, Leakage, Pipes, Pressure, Sensors, Sprays, Temperature, Temperature distribution
Journal Articles

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

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Norihiro Kikuchi, Yasutomo Imai, Ryuji Yoshikawa, Norihiro Doda, Masaaki Tanaka, Hiroyuki Ohshima
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
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 Articletitled, Subchannel Analysis of Thermal-Hydraulics in a Fuel Assembly With Inner Duct Structure of a Sodium-Cooled Fast Reactor
Open the PDF for Subchannel Analysis of Thermal-Hydraulics in a Fuel Assembly With Inner Duct Structure of a Sodium-Cooled Fast Reactor in another window
Topics: Ducts, Flow (Dynamics), Fuels, Manufacturing, Sodium, Temperature distribution, Temperature, Sodium fast reactors, Wire, Thermal hydraulics
Journal Articles

Burn-Up Dependency of Control Rod Position at Zero-Power Criticality in the High-Temperature Engineering Test Reactor

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Yuki Honda, Nozomu Fujimoto, Hiroaki Sawahata, Shoji Takada, Kazuhiro Sawa
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research Papers
ASME J of Nuclear Rad Sci. January 2017, 3(1): 011013.
Paper No: NERS-15-1220
https://doi.org/10.1115/1.4033812
Published Online: December 20, 2016
View Articletitled, Burn-Up Dependency of Control Rod Position at Zero-Power Criticality in the High-Temperature Engineering Test Reactor
Open the PDF for Burn-Up Dependency of Control Rod Position at Zero-Power Criticality in the High-Temperature Engineering Test Reactor in another window
Topics: Evaluation methods, High temperature, Temperature, Design, Cycles, Temperature distribution, Physics, Very high temperature reactors
Journal Articles

Temperature Distribution Inside Fresh-Fuel Pins of Pressure-Tube Supercritical-Water-Cooled Reactor

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Vitali Kovaltchouk, Eleodor Nichita, Eugene Saltanov
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research Papers
ASME J of Nuclear Rad Sci. January 2016, 2(1): 011008.
Paper No: NERS-15-1057
https://doi.org/10.1115/1.4031163
Published Online: December 9, 2015
View Articletitled, Temperature Distribution Inside Fresh-Fuel Pins of Pressure-Tube Supercritical-Water-Cooled Reactor
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Topics: Fuels, Pins (Engineering), Temperature distribution, Temperature, Water, Pressure
Journal Articles

Numerical Study of High-Temperature and High-Velocity Gaseous Hydrogen Flow in a Cooling Channel of a Nuclear Thermal Rocket Core

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Kazim M. Akyuzlu
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research Papers
ASME J of Nuclear Rad Sci. October 2015, 1(4): 041006.
Paper No: NERS-15-1014
https://doi.org/10.1115/1.4030833
Published Online: September 3, 2015
View Articletitled, Numerical Study of High-Temperature and High-Velocity Gaseous Hydrogen Flow in a Cooling Channel of a Nuclear Thermal Rocket Core
Open the PDF for Numerical Study of High-Temperature and High-Velocity Gaseous Hydrogen Flow in a Cooling Channel of a Nuclear Thermal Rocket Core in another window
Topics: Computational fluid dynamics, Cooling, Engines, Flow (Dynamics), Fluids, Fuels, Heat flux, Hydrogen, Pressure, Temperature
Journal Articles

Erratum: “Numerical Simulation of Temperature Distribution in a Containment Vessel of an Operating PWR Plant” [Journal of Nuclear Engineering and Radiation Science, 2015, 1(1), p. 011002-4-011002-8, DOI: 10.1115/1.4026389]

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Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Errata
ASME J of Nuclear Rad Sci. October 2015, 1(4): 047001.
Paper No: NERS-15-1110
https://doi.org/10.1115/1.4031143
Published Online: September 3, 2015
View Articletitled, Erratum: “Numerical Simulation of Temperature Distribution in a Containment Vessel of an Operating PWR Plant” [Journal of Nuclear Engineering and Radiation Science, 2015, 1(1), p. 011002-4-011002-8, DOI: 10.1115/1.4026389]
Open the PDF for Erratum: “Numerical Simulation of Temperature Distribution in a Containment Vessel of an Operating PWR Plant” [Journal of Nuclear Engineering and Radiation Science, 2015, 1(1), p. 011002-4-011002-8, DOI: 10.1115/1.4026389] in another window
Topics: Computer simulation, Containment vessels, Nuclear engineering, Pressurized water reactors, Radiation (Physics), Temperature distribution
Journal Articles

Numerical Simulation of Temperature Distribution in a Containment Vessel of an Operating PWR Plant

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Yoichi Utanohara, Michio Murase, Akihiro Masui, Ryo Inomata, Yuji Kamiya
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research Papers
ASME J of Nuclear Rad Sci. January 2015, 1(1): 011002.
Paper No: NERS-14-1004
https://doi.org/10.1115/1.4026389
Published Online: February 9, 2015
View Articletitled, Numerical Simulation of Temperature Distribution in a Containment Vessel of an Operating PWR Plant
Open the PDF for Numerical Simulation of Temperature Distribution in a Containment Vessel of an Operating PWR Plant in another window
Topics: Computer simulation, Flow (Dynamics), Pressurized water reactors, Temperature, Temperature distribution, Containment vessels, Heat, Simulation