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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

Influence of Noncondensable Gas–Dust Mixture on Direct Contact Condensation of Steam at Atmospheric Pressure

Luca Berti, Alessio Pesetti, Michele Raucci, Guglielmo Giambartolomei, Donato Aquaro
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2024, 10(1): 012301.
Paper No: NERS-23-1020
https://doi.org/10.1115/1.4064066
Published Online: November 30, 2023
View Article titled, Influence of Noncondensable Gas–Dust Mixture on Direct Contact Condensation of Steam at Atmospheric Pressure
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Topics: Condensation, Dust, Steam, Water, Temperature
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

Dimensionless Profiles of Temperature and Steam Mass Fraction in Flows of Steam-Air Mixtures on a Flat Plate

Michio Murase, Tomonori Suzuki, Yoichi Utanohara, Toshiya Takaki
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2023, 9(1): 011401.
Paper No: NERS-22-1006
https://doi.org/10.1115/1.4054842
Published Online: July 19, 2022
View Article titled, Dimensionless Profiles of Temperature and Steam Mass Fraction in Flows of Steam-Air Mixtures on a Flat Plate
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Topics: Flow (Dynamics), Steam, Temperature, Turbulence, Condensation, Flat plates, Boundary layer turbulence, Computational fluid dynamics, Computation
Journal Articles

Flash-Boiling Characterization During Ingress of Coolant Event for Dust Issue in ITER

Benjamin Blaisot, Emmanuel Porcheron, Olivier Praud, Véronique Roig
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2022, 8(3): 032301.
Paper No: NERS-21-1149
https://doi.org/10.1115/1.4053828
Published Online: June 1, 2022
View Article titled, Flash-Boiling Characterization During Ingress of Coolant Event for Dust Issue in ITER
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Topics: Boiling, Coolants, Drops, Dust, Ejectors, Flow (Dynamics), Pressure, Sprays, Vacuum, Water
Journal Articles

Thermal-Hydraulic Safety Assessment of Full-Scale ESBWR Nuclear Reactor Design

S. P. Saraswat, D. Ray, G. Mishra, D. Yadav, V. S. Bhadouria, P. Munshi, C. Allison
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2022, 8(3): 031403.
Paper No: NERS-21-1073
https://doi.org/10.1115/1.4052014
Published Online: May 26, 2022
View Article titled, Thermal-Hydraulic Safety Assessment of Full-Scale ESBWR Nuclear Reactor Design
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Topics: Accidents, Boiling water reactors, Containment, Design, Pressure, Safety, Steam, Water, Heat, Economics
Journal Articles

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

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 Article titled, Prediction Method for Condensation Heat Transfer in the Presence of Noncondensable Gas for Computational Fluid Dynamics Applications
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Topics: Condensation, Heat transfer, Steam, Temperature, Temperature distribution, Computational fluid dynamics, Mass transfer, Flat plates
Journal Articles

Simulated Environmental Tests for Selected Advanced Technology Fuel Cladding Solutions

Sami Penttilä, Juha-Matti Autio, Jari Lydman, Aki Toivonen, Seppo Peltonen, Johanna Lukin
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2022, 8(3): 031103.
Paper No: NERS-21-1069
https://doi.org/10.1115/1.4052974
Published Online: March 15, 2022
View Article titled, Simulated Environmental Tests for Selected Advanced Technology Fuel Cladding Solutions
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Topics: Cladding systems (Building), Coatings, Fracture (Materials), Fuels, High temperature steam, Pressurized water reactors, Steam, Zirconium, Temperature, Weight (Mass)
Journal Articles

Design of Condensation Heat Transfer Experiment to Evaluate Scaling Distortion in Small Modular Reactor Safety Analysis

Palash K. Bhowmik, J. P. Schlegel, V. Kalra, C. Mills, S. Usman
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2021, 7(3): 031406.
Paper No: NERS-20-1021
https://doi.org/10.1115/1.4050211
Published Online: April 16, 2021
View Article titled, Design of Condensation Heat Transfer Experiment to Evaluate Scaling Distortion in Small Modular Reactor Safety Analysis
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Topics: Condensation, Cooling, Design, Flow (Dynamics), Heat transfer, Steam, Test facilities, Temperature, Pressure, Water
Journal Articles

Methodology for Calculating Minor Radioactive Releases From VVER 1000 Using TRACE Code

M. Ruscak, G. Mazzini, A. Dambrosio, A. Musa
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2021, 7(2): 021402.
Paper No: NERS-20-1208
https://doi.org/10.1115/1.4049854
Published Online: February 26, 2021
View Article titled, Methodology for Calculating Minor Radioactive Releases From VVER 1000 Using TRACE Code
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Topics: Accidents, Coolants, Flow (Dynamics), Pressure, Safety, Simulation, Water, Nuclear power stations, Feedwater, Design
Journal Articles

Optimization of the PGV-1000MKO Steam Generator Using Computation Fluid Dynamics

Vasilii Volkov, Luka Golibrodo, Alexey Krutikov, Oleg Kudryavtsev, Yurii Nadinskii, Alexander Skibin, Vladimir Sotskov
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2021, 7(3): 031403.
Paper No: NERS-19-1162
https://doi.org/10.1115/1.4048234
Published Online: February 19, 2021
View Article titled, Optimization of the PGV-1000MKO Steam Generator Using Computation Fluid Dynamics
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Topics: Flow (Dynamics), Nozzles, Steam, Evaporation, Boilers, Optimization
Journal Articles

Nonhyperbolicity of Conservation Equations of RELAP5 Two-Fluid Model in Nuclear Reactor Safety Results (Investigation and Eigenvalue Analysis)

S. P. Saraswat, P. Munshi, C. Allison
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2021, 7(1): 011402.
Paper No: NERS-19-1022
https://doi.org/10.1115/1.4047161
Published Online: October 2, 2020
View Article titled, Nonhyperbolicity of Conservation Equations of RELAP5 Two-Fluid Model in Nuclear Reactor Safety Results (Investigation and Eigenvalue Analysis)
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Topics: Accidents, Boiling water reactors, Eigenvalues, Fluids, Porosity, Pressure, Pressurized water reactors, Light water reactors, Water, Stability
Journal Articles

Steam Condensation Heat Transfer During Initial Blow-Down Period of a Severe Nuclear Accident

Mahesh Kumar Yadav, Maneesh Punetha, Abhinav Bhanawat, Sameer Khandekar, Pavan K. Sharma
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2020, 6(4): 041108.
Paper No: NERS-19-1164
https://doi.org/10.1115/1.4046910
Published Online: September 4, 2020
View Article titled, Steam Condensation Heat Transfer During Initial Blow-Down Period of a Severe Nuclear Accident
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Topics: Accidents, Condensation, Heat flux, Heat transfer, Pressure, Steady state, Steam, Temperature, Transients (Dynamics), Containment
Journal Articles

Analysis Methods for High Energy Line Break Jet Flows in Nuclear Power Plants

Marwan Charrouf, Storm Kauffman, Jin-Kyoo Yoon, Sang-Gyu Lee, Taejoon Kim
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2020, 6(4): 041112.
Paper No: NERS-19-1168
https://doi.org/10.1115/1.4047441
Published Online: September 4, 2020
View Article titled, Analysis Methods for High Energy Line Break Jet Flows in Nuclear Power Plants
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Topics: Computational fluid dynamics, Flow (Dynamics), Jets, Nozzles, Nuclear power stations, Pipes, Pressure, Reflection, Resonance, Waves
Journal Articles

Analysis of the Effect of Vessel Failure and Melt Release on Risk of Containment Failure Due to Ex-Vessel Steam Explosion in Nordic Boiling Water Reactor Using ROAAM+ Framework

Sergey Galushin, Dmitry Grishchenko, Pavel Kudinov
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2020, 6(4): 041113.
Paper No: NERS-19-1170
https://doi.org/10.1115/1.4047552
Published Online: September 4, 2020
View Article titled, Analysis of the Effect of Vessel Failure and Melt Release on Risk of Containment Failure Due to Ex-Vessel Steam Explosion in Nordic Boiling Water Reactor Using ROAAM+ Framework
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Topics: Boiling water reactors, Containment, Explosions, Failure, Steam, Vessels, Risk, Accidents, Uncertainty
Journal Articles

Oxidation Behavior of Alumina-Forming Austenitic Steels in Superheated Steam at 700 °C

Bingjie Xiao, Nick Tepylo, Xiao Huang, Zhangjian Zhou, Sami Penttilä
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2020, 6(3): 031109.
Paper No: NERS-19-1078
https://doi.org/10.1115/1.4044530
Published Online: June 5, 2020
View Article titled, Oxidation Behavior of Alumina-Forming Austenitic Steels in Superheated Steam at 700 °C
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Topics: Alloys, Oxidation, Steam, Steel, Superheating, Weight (Mass), Spallation (Nuclear physics)
Journal Articles

Numerical Simulation of a Steam Injector for Passive Residual Heat Removal

Thomas Schulenberg, David Heinze
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2020, 6(3): 031105.
Paper No: NERS-19-1058
https://doi.org/10.1115/1.4045692
Published Online: June 5, 2020
View Article titled, Numerical Simulation of a Steam Injector for Passive Residual Heat Removal
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Topics: Ejectors, Flow (Dynamics), Nozzles, Pressure, Shock (Mechanics), Steam, Condensation, Computer simulation, Water, Two-phase flow
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

Enhanced Accident Tolerance of Thoria-Based Nuclear Fuels

B. Szpunar, J. A. Szpunar
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2020, 6(1): 011108.
Paper No: NERS-19-1046
https://doi.org/10.1115/1.4044751
Published Online: November 8, 2019
View Article titled, Enhanced Accident Tolerance of Thoria-Based Nuclear Fuels
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Topics: Accidents, Atoms, Diffusion (Physics), Fuel rods, Fuels, Helium, Nuclear fuels, Oxygen, Temperature, Temperature gradient
Journal Articles

Effect of Steam Temperature and Pressure on the Oxidation of Potential Coating Alloy FeCrAl for Supercritical Water-Cooled Reactor Application

Bingjie Xiao, Xiao Huang, Qi Yang, Prakash Patnaik
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2019, 5(4): 041204.
Paper No: NERS-18-1081
https://doi.org/10.1115/1.4042500
Published Online: July 19, 2019
View Article titled, Effect of Steam Temperature and Pressure on the Oxidation of Potential Coating Alloy FeCrAl for Supercritical Water-Cooled Reactor Application
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Topics: Alloys, Coatings, Oxidation, Pressure, Steam, Superheating, Temperature, Water, Weight (Mass), High temperature