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Journal Articles

Heat Flux Correlations for Condensation from Steam and Air Mixtures on Vertical Flat Plates

Accepted Manuscript
Michio Murase, Toshiya Takaki
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci.
Paper No: NERS-24-1021
https://doi.org/10.1115/1.4066343
Published Online: August 26, 2024
View Article titled, Heat Flux Correlations for Condensation from Steam and Air Mixtures on Vertical Flat Plates
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Topics: Condensation, Flat plates, Heat flux, Steam, Computational fluid dynamics, Flow (Dynamics), Natural convection, Accidents, Boundary-value problems, Containment vessels
Journal Articles

Uncertainty and Sensitivity Evaluation of the QUENCH-02 Experiment Simulation Using the ASYST Code

Siniša Šadek, Renato Pavlinac, Karlo Ivanjko, Davor Grgić
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2024, 10(1): 011301.
Paper No: NERS-23-1016
https://doi.org/10.1115/1.4062799
Published Online: October 20, 2023
View Article titled, Uncertainty and Sensitivity Evaluation of the QUENCH-02 Experiment Simulation Using the ASYST Code
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Topics: Cladding systems (Building), Electricity (Physics), Flow (Dynamics), Hydrogen, Oxidation, Steam, Temperature, Uncertainty, Water, Boundary-value problems
Journal Articles

Development of a Phase-Field Method for Phase Change Simulations Using a Conservative Allen–Cahn Equation

Akinori Tamura, Kenichi Katono
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2022, 8(3): 031402.
Paper No: NERS-21-1068
https://doi.org/10.1115/1.4052807
Published Online: May 26, 2022
View Article titled, Development of a Phase-Field Method for Phase Change Simulations Using a Conservative Allen–Cahn Equation
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Topics: Boundary-value problems, Simulation, Wetting, Vapors, Bubbles, Simulation results
Journal Articles

Development of a Phase-Field Method for Phase Change Simulations Using a Conservative Allen–Cahn Equation

Akinori Tamura, Kenichi Katono
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2022, 8(2): 021401.
Paper No: NERS-20-1182
https://doi.org/10.1115/1.4050209
Published Online: October 19, 2021
View Article titled, Development of a Phase-Field Method for Phase Change Simulations Using a Conservative Allen–Cahn Equation
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Topics: Boundary-value problems, Simulation, Wetting, Vapors, Bubbles, Simulation results
Journal Articles

Numerical Study of the Deposition of Radioactive Nuclide (Aerosol) in Pressurized Water Reactor Steam Generator

Muhammad Aadil, Rab Nawaz, Ajmal Shah, Kamran Rasheed Qureshi
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2022, 8(2): 021801.
Paper No: NERS-20-1210
https://doi.org/10.1115/1.4051618
Published Online: October 19, 2021
View Article titled, Numerical Study of the Deposition of Radioactive Nuclide (Aerosol) in Pressurized Water Reactor Steam Generator
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Topics: Aerosols, Boilers, Decontamination, Nuclides, Particulate matter, Pressurized water reactors, Turbulence, Computational fluid dynamics, Flow (Dynamics), Particle size
Journal Articles

Improved Computational Fluid Dynamics Framework for Reactor Core Baffle Swelling Assessment

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 Article titled, 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

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
Publisher: ASME
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

Analyses of Gas Stratification Erosion by a Vertical Jet in Presence of an Obstacle Using the GOTHIC Code

Michele Andreani, Ralf Kapulla, Stephan Kelm, Domenico Paladino, Sidharth Paranjape
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2020, 6(2): 021110.
Paper No: NERS-19-1072
https://doi.org/10.1115/1.4046296
Published Online: February 24, 2020
View Article titled, Analyses of Gas Stratification Erosion by a Vertical Jet in Presence of an Obstacle Using the GOTHIC Code
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Topics: Elevations (Drawings), Erosion, Flow (Dynamics), Helium, Pipes, Simulation, Steam, Temperature, Turbulence, Vessels
Journal Articles

RELAP5-3D Three-Dimensional Analysis Based on PHÉNIX Dissymmetric Transient Test

Vincenzo Narcisi, Fabio Giannetti, Andrea Subioli, Alessandro Del Nevo, Gianfranco Caruso
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2020, 6(1): 011301.
Paper No: NERS-19-1001
https://doi.org/10.1115/1.4044847
Published Online: November 29, 2019
View Article titled, RELAP5-3D Three-Dimensional Analysis Based on PHÉNIX Dissymmetric Transient Test
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Topics: Coolants, Flow (Dynamics), Modeling, Pipes, Pumps, Sodium, Temperature, Transients (Dynamics), Vessels, Three-dimensional models
Journal Articles

Hydrogen–Air–Steam Deflagration Experiment Simulated Using Different Turbulent Flame-Speed Closure Models

Holler Tadej, Ed M. J. Komen, Kljenak Ivo
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2018, 4(3): 031009.
Paper No: NERS-16-1126
https://doi.org/10.1115/1.4039067
Published Online: May 16, 2018
View Article titled, Hydrogen–Air–Steam Deflagration Experiment Simulated Using Different Turbulent Flame-Speed Closure Models
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Topics: Combustion, Explosions, Flames, Hydrogen, Turbulence, Pressure, Computational fluid dynamics, Simulation, Boundary-value problems
Journal Articles

Summary on the Results of Two Computational Fluid Dynamic Benchmarks of Tube and Different Channel Geometries

Attila Kiss, Andrey Churkin, Darwan S. Pilkhwal, Abhijeet M. Vaidya, Walter Ambrosini, Andrea Pucciarelli, Krishna Podila, Yanfei Rao, Laurence Leung, Chen Yuzhou, Mark Anderson, Meng Zhao
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2018, 4(1): 011001.
Paper No: NERS-17-1047
https://doi.org/10.1115/1.4038162
Published Online: December 4, 2017
View Article titled, Summary on the Results of Two Computational Fluid Dynamic Benchmarks of Tube and Different Channel Geometries
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Topics: Computational fluid dynamics, Sensitivity analysis, Wall temperature, Heat transfer, Turbulence, Boundary-value problems
Journal Articles

An Experimental and Numerical Study to Support Development of Molten Salt Breeder Reactor

A. K. Srivastava, R. Chouhan, A. Borgohain, S. S. Jana, N. K. Maheshwari, D. S. Pilkhwal, A. Rama Rao, K. N. Hareendhran, S. Chowdhury, K. B. Modi, S. K. Raut, S. C. Parida
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2017, 3(3): 031007.
Paper No: NERS-16-1154
https://doi.org/10.1115/1.4036027
Published Online: May 25, 2017
View Article titled, An Experimental and Numerical Study to Support Development of Molten Salt Breeder Reactor
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Topics: Boundary-value problems, Breeder reactors, Computational fluid dynamics, Flow (Dynamics), Simulation, Steady state, Temperature, Transients (Dynamics), Fluids, Instrumentation
Journal Articles

Influence of Boundary Conditions, Vessel Geometry, and Simulant Materials on the Heat Transfer of Volumetrically Heated Melt in a Light Water Reactor Lower Head

X. Gaus-Liu, A. Miassoedov
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2017, 3(3): 031003.
Paper No: NERS-16-1107
https://doi.org/10.1115/1.4035853
Published Online: May 25, 2017
View Article titled, Influence of Boundary Conditions, Vessel Geometry, and Simulant Materials on the Heat Transfer of Volumetrically Heated Melt in a Light Water Reactor Lower Head
Open the PDF for Influence of Boundary Conditions, Vessel Geometry, and Simulant Materials on the Heat Transfer of Volumetrically Heated Melt in a Light Water Reactor Lower Head in another window
Topics: Boundary-value problems, Cooling, Heat flux, Heat transfer, Temperature, Vessels, Geometry, Insulation, Water
Journal Articles

The Powerful Method of Characteristics Module in Advanced Neutronics Lattice Code KYLIN-2

Xiaoming Chai, Xiaolan Tu, Wei Lu, Zongjian Lu, Dong Yao, Qing Li, Wenbin Wu
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2017, 3(3): 031004.
Paper No: NERS-16-1110
https://doi.org/10.1115/1.4035934
Published Online: May 25, 2017
View Article titled, The Powerful Method of Characteristics Module in Advanced Neutronics Lattice Code KYLIN-2
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Topics: Boundary-value problems, Reflection, Trajectories (Physics), Geometry, Rotation
Journal Articles

Computational Fluid Dynamics Investigation of Supercritical Water Flow and Heat Transfer in a Rod Bundle With Grid Spacers

Malwina Gradecka, Roman Thiele, Henryk Anglart
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research Papers
ASME J of Nuclear Rad Sci. July 2016, 2(3): 031015.
Paper No: NERS-15-1087
https://doi.org/10.1115/1.4032635
Published Online: June 17, 2016
View Article titled, Computational Fluid Dynamics Investigation of Supercritical Water Flow and Heat Transfer in a Rod Bundle With Grid Spacers
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Topics: Computational fluid dynamics, Flow (Dynamics), Fuel rods, Heat transfer, Rods, Temperature, Water, Geometry, Boundary-value problems, Fluids
Journal Articles

Computational Fluid Dynamics Prediction of Heat Transfer in Rod Bundles With Water at Supercritical Pressure

Andrea Pucciarelli, Walter Ambrosini
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research Papers
ASME J of Nuclear Rad Sci. January 2016, 2(1): 011011.
Paper No: NERS-15-1090
https://doi.org/10.1115/1.4031201
Published Online: December 9, 2015
View Article titled, Computational Fluid Dynamics Prediction of Heat Transfer in Rod Bundles With Water at Supercritical Pressure
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Topics: Boundary-value problems, Computational fluid dynamics, Geometry, Heat transfer, Pressure, Turbulence, Wall temperature, Water, Flow (Dynamics), Temperature
Journal Articles

Countercurrent Flow Limitation in Slightly Inclined Pipes With Elbows

Michio Murase, Ikuo Kinoshita, Takayoshi Kusunoki, Dirk Lucas, Akio Tomiyama
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research Papers
ASME J of Nuclear Rad Sci. October 2015, 1(4): 041009.
Paper No: NERS-15-1019
https://doi.org/10.1115/1.4031032
Published Online: September 3, 2015
View Article titled, Countercurrent Flow Limitation in Slightly Inclined Pipes With Elbows
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Topics: Computation, Flow (Dynamics), Pipes, Surges, Water, Boundary-value problems, Drag (Fluid dynamics), Friction, Pressure
Journal Articles

Fully Coupled Simulation of Oxygen and Heat Diffusion for ( U , Pu ) O 2 Fuel in Both Fast-Breeder Reactor and Light-Water Reactor

Wenzhong Zhou, Rong Liu
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research Papers
ASME J of Nuclear Rad Sci. October 2015, 1(4): 041007.
Paper No: NERS-15-1020
https://doi.org/10.1115/1.4031033
Published Online: September 3, 2015
View Article titled, Fully Coupled Simulation of Oxygen and Heat Diffusion for ( U , Pu ) O 2 Fuel in Both Fast-Breeder Reactor and Light-Water Reactor
Open the PDF for Fully Coupled Simulation of Oxygen and Heat Diffusion for ( U , Pu ) O 2 Fuel in Both Fast-Breeder Reactor and Light-Water Reactor in another window
Topics: Fuels, Light water reactors, Oxygen, Simulation, Temperature, Fast neutron reactors, Diffusion (Physics), Heat, Boundary-value problems, Thermal diffusion
Journal Articles

Analysis of Focusing Effect of Light Metallic Layer in Stratified Molten Pool Under IVR-ERVC Condition

Xi Wang, Xu Cheng
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research Papers
ASME J of Nuclear Rad Sci. April 2015, 1(2): 021007.
Paper No: NERS-14-1001
https://doi.org/10.1115/1.4029619
Published Online: March 24, 2015
View Article titled, Analysis of Focusing Effect of Light Metallic Layer in Stratified Molten Pool Under IVR-ERVC Condition
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Topics: Computational fluid dynamics, Heat flux, Heat transfer, Metals, Temperature, Boundary-value problems, Heat