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Journal Articles

Mechanical and Microstructural Characterization of Inconel 625 Welds After Corrosion at Supercritical Water Conditions

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German Cota-Sanchez, Lin Xiao, Stephane Rousseau
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2022, 8(3): 031107.
Paper No: NERS-22-1007
https://doi.org/10.1115/1.4054637
Published Online: May 25, 2022
View Article titled, Mechanical and Microstructural Characterization of Inconel 625 Welds After Corrosion at Supercritical Water Conditions
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Topics: Corrosion, Welding, Phase diagrams, Water, Welded joints, Testing
Journal Articles

Joining of Zirconium Alloys to Nickel Bearing Alloys for In-Core Components

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Michel Gaudet, Anne McLellan, Adrian Gerlich, Bruce Williams
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Technical Briefs
ASME J of Nuclear Rad Sci. July 2022, 8(3): 031106.
Paper No: NERS-21-1087
https://doi.org/10.1115/1.4054557
Published Online: May 17, 2022
View Article titled, Joining of Zirconium Alloys to Nickel Bearing Alloys for In-Core Components
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Topics: Alloys, Extruding, Friction welding, Zirconium alloys, Stainless steel, Bearings, Zirconium, Friction, Nickel, Supercritical water reactors
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 Article titled, Testing the Modified Subchannel tempa-sc Code in Comparison With Experiments and Other Computer Codes
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Topics: Coolants, Fluids, Fuel rods, Heat transfer, Momentum, Temperature, Water, Wall temperature, Flow (Dynamics), Testing
Journal Articles

Concept of a Small Modular SCWR With Horizontal Fuel Assemblies

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Thomas Schulenberg, Ivan Otic
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Technical Briefs
ASME J of Nuclear Rad Sci. July 2022, 8(3): 031104.
Paper No: NERS-21-1074
https://doi.org/10.1115/1.4052191
Published Online: March 15, 2022
View Article titled, Concept of a Small Modular SCWR With Horizontal Fuel Assemblies
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Topics: Coolants, Design, Fuels, Heat, Supercritical water reactors, Water, Temperature, Light water reactors, Cladding systems (Building), Natural convection
Journal Articles

Weight Gain and Hydrogen Absorption in Supercritical Water At 500 °C of Chromium-Coated Zirconium-Based Alloys: Transverse Versus Longitudinal Direction

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K. Khumsa-Ang, S. Rousseau, O. Shiman
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2022, 8(3): 031102.
Paper No: NERS-21-1065
https://doi.org/10.1115/1.4052520
Published Online: March 15, 2022
View Article titled, Weight Gain and Hydrogen Absorption in Supercritical Water At 500 °C of Chromium-Coated Zirconium-Based Alloys: Transverse Versus Longitudinal Direction
Open the PDF for Weight Gain and Hydrogen Absorption in Supercritical Water At 500 °C of Chromium-Coated Zirconium-Based Alloys: Transverse Versus Longitudinal Direction in another window
Topics: Alloys, Coatings, Corrosion, Hydrogen, Water, Weight (Mass), Zirconium, Absorption, Coating processes, Zirconium alloys
Journal Articles

Simulated Environmental Tests for Selected Advanced Technology Fuel Cladding Solutions

Open Access
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

Deteriorated Heat Transfer Influence on the Stress–Strain State of Small Modular Reactors SCWR Fuel Bundles

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Y. Dubyk, V. Filonov, Y. Filonova, O. Kovalenko
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2022, 8(3): 031105.
Paper No: NERS-21-1082
https://doi.org/10.1115/1.4052590
Published Online: March 15, 2022
View Article titled, Deteriorated Heat Transfer Influence on the Stress–Strain State of Small Modular Reactors SCWR Fuel Bundles
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Topics: Computational fluid dynamics, Heat transfer, Stress, Supercritical water reactors, Temperature, Fuels, Small modular reactors
Journal Articles

Investigations of Rod Positions for Treat M8CAL Analyses

Free
Zachary Weems, Sedat Goluoglu, Mark D. DeHart
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2018, 4(3): 031017.
Paper No: NERS-17-1071
https://doi.org/10.1115/1.4038929
Published Online: May 16, 2018
View Article titled, Investigations of Rod Positions for Treat M8CAL Analyses
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Journal Articles

Crack Growth and Tolerance of Stainless Steel Canisters in the Marine Environment

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Chang Heui-Yung
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2018, 4(3): 031022.
Paper No: NERS-17-1209
https://doi.org/10.1115/1.4039501
Published Online: May 16, 2018
View Article titled, Crack Growth and Tolerance of Stainless Steel Canisters in the Marine Environment
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Journal Articles

Correlation of Interfacial Friction Coefficients for Predicting Countercurrent Flow Limitation at a Sharp-Edged Lower End of Vertical Pipes

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Michio Murase, Takayoshi Kusunoki, Koji Nishida, Raito Goda, Akio Tomiyama
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2018, 4(3): 031001.
Paper No: NERS-17-1057
https://doi.org/10.1115/1.4039438
Published Online: May 16, 2018
View Article titled, Correlation of Interfacial Friction Coefficients for Predicting Countercurrent Flow Limitation at a Sharp-Edged Lower End of Vertical Pipes
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Topics: Computation, Flow (Dynamics), Pipes, Water, Friction, Steam, High pressure (Physics)
Journal Articles

Verifying Calculation of the Parameters of AP1000 Core Design Based on MCNP Model

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Xiong Wenbin, Cao Jian, Huang Chaoyun, Bie Yewang, Wang Yanqi, Li Jufeng
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2018, 4(3): 031018.
Paper No: NERS-17-1132
https://doi.org/10.1115/1.4039596
Published Online: May 16, 2018
View Article titled, Verifying Calculation of the Parameters of AP1000 Core Design Based on MCNP Model
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Topics: Design, Fuels, Rods, Manufacturing, Nuclear power stations, Modeling, Boron, Physics
Journal Articles

Numerical Investigation of Convective Heat Transfer to Supercritical Pressure Hydrogen in a Straight Tube

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Yu Ji, Jun Sun, Lei Shi
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2018, 4(3): 031012.
Paper No: NERS-17-1193
https://doi.org/10.1115/1.4039600
Published Online: May 16, 2018
View Article titled, Numerical Investigation of Convective Heat Transfer to Supercritical Pressure Hydrogen in a Straight Tube
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Topics: Convection, Heat transfer, Hydrogen, Pressure, Simulation, Turbulence, Flow (Dynamics), Density, Temperature, Viscosity
Journal Articles

Parallel Analysis of Linear Systems in CORTH and KYLIN2

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Pingzhou Ming, Dingyong Chen, Bin Wu, Wei Lu, Dong Liu, Hongxing Yu
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2018, 4(3): 031010.
Paper No: NERS-17-1143
https://doi.org/10.1115/1.4039036
Published Online: May 16, 2018
View Article titled, Parallel Analysis of Linear Systems in CORTH and KYLIN2
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Topics: Linear systems, Thermal hydraulics, Manufacturing, Cores (Molding materials)
Journal Articles

Effect of Lead-Bismuth Eutectic Oxygen Concentration on the Onset of Dissolution Corrosion in 316 L Austenitic Stainless Steel at 450 °C

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Oksana Klok, Konstantina Lambrinou, Serguei Gavrilov, Jun Lim, Iris De Graeve
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2018, 4(3): 031019.
Paper No: NERS-17-1269
https://doi.org/10.1115/1.4039598
Published Online: May 16, 2018
View Article titled, Effect of Lead-Bismuth Eutectic Oxygen Concentration on the Onset of Dissolution Corrosion in 316 L Austenitic Stainless Steel at 450 °C
Open the PDF for Effect of Lead-Bismuth Eutectic Oxygen Concentration on the Onset of Dissolution Corrosion in 316 L Austenitic Stainless Steel at 450 °C in another window
Topics: Corrosion, Oxygen, Stainless steel, Steel
Journal Articles

Mechanical Properties of Cubic (U,Zr)O 2

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Toru Kitagaki, Takanori Hoshino, Kimihiko Yano, Nobuo Okamura, Hiroshi Ohara, Tetsuo Fukasawa, Kenji Koizumi
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2018, 4(3): 031011.
Paper No: NERS-17-1069
https://doi.org/10.1115/1.4039847
Published Online: May 16, 2018
View Article titled, Mechanical Properties of Cubic (U,Zr)O 2
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Topics: Elastic moduli, Fracture toughness, Mechanical properties, Vickers hardness testing, Zirconium, Fracture (Materials), Fuels, Solid solutions
Journal Articles

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

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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

Experimental Study on Melt Coolability Capability of Calandria Vault Water During Severe Accident in Indian PHWRs for Prolonged Duration

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Sumit V. Prasad, A. K. Nayak
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2018, 4(3): 031014.
Paper No: NERS-17-1062
https://doi.org/10.1115/1.4039636
Published Online: May 16, 2018
View Article titled, Experimental Study on Melt Coolability Capability of Calandria Vault Water During Severe Accident in Indian PHWRs for Prolonged Duration
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Topics: Accidents, Boiling, Heat transfer, Heat transfer coefficients, Heavy water reactors, Temperature, Vessels, Water, Heat, Natural convection
Journal Articles

Method and Validation for Measurement of Effective Thermal Diffusivity and Conductivity of Pebble Bed in High Temperature Gas-Cooled Reactors

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Yongyong Wu, Cheng Ren, Rui Li, Xingtuan Yang, Jiyuan Tu, Shengyao Jiang
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2018, 4(3): 031006.
Paper No: NERS-17-1109
https://doi.org/10.1115/1.4039035
Published Online: May 16, 2018
View Article titled, Method and Validation for Measurement of Effective Thermal Diffusivity and Conductivity of Pebble Bed in High Temperature Gas-Cooled Reactors
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Topics: Errors, Temperature, Thermal conductivity, Thermal diffusivity, Very high temperature reactors, Low temperature, Safety, Heat conduction, Algorithms, Electrical conductivity
Journal Articles

Analysis of Inertization Strategies for the Filtered Containment Venting System in Cofrentes Nuclear Power Plant

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Kevin Fernández-Cosials, Gonzalo Jiménez, César Serrano, Luisa Ibáñez, Ángel Peinado
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2018, 4(3): 031016.
Paper No: NERS-17-1065
https://doi.org/10.1115/1.4038595
Published Online: May 16, 2018
View Article titled, Analysis of Inertization Strategies for the Filtered Containment Venting System in Cofrentes Nuclear Power Plant
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Topics: Containment, Hydrogen, Nitrogen, Nuclear power stations, Oxygen, Risk, Combustion, Simulation
Journal Articles

Multiphysics Modeling of Pressurized Water Reactor Fuel Performance

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Wang Zhu, Zhang Chungyu, Yuan Cenxi
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2018, 4(3): 031008.
Paper No: NERS-17-1103
https://doi.org/10.1115/1.4039848
Published Online: May 16, 2018
View Article titled, Multiphysics Modeling of Pressurized Water Reactor Fuel Performance
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Topics: Cladding systems (Building), Fuel rods, Fuels, Modeling, Nuclear fission, Temperature, Pressurized water reactors, Stress, Accidents