1-20 of 68
Special Section Papers
Close
Save search
Follow your search
Access your saved searches in your account
Would you like to receive an alert when new items match your search?
Close Modal
Sort by
Journal Articles

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

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
Open the PDF for Mechanical and Microstructural Characterization of Inconel 625 Welds After Corrosion at Supercritical Water Conditions in another window
Topics: Corrosion, Welding, Phase diagrams, Water, Welded joints, Testing
Journal Articles

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

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
Open the PDF for Joining of Zirconium Alloys to Nickel Bearing Alloys for In-Core Components in another window
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

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
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

Concept of a Small Modular SCWR With Horizontal Fuel Assemblies

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
Open the PDF for Concept of a Small Modular SCWR With Horizontal Fuel Assemblies in another window
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

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

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
Open the PDF for Simulated Environmental Tests for Selected Advanced Technology Fuel Cladding Solutions in another window
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

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
Open the PDF for Deteriorated Heat Transfer Influence on the Stress–Strain State of Small Modular Reactors SCWR Fuel Bundles in another window
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

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
Open the PDF for Investigations of Rod Positions for Treat M8CAL Analyses in another window
Journal Articles

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

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
Open the PDF for Crack Growth and Tolerance of Stainless Steel Canisters in the Marine Environment in another window
Journal Articles

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

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
Open the PDF for Correlation of Interfacial Friction Coefficients for Predicting Countercurrent Flow Limitation at a Sharp-Edged Lower End of Vertical Pipes in another window
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

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
Open the PDF for Verifying Calculation of the Parameters of AP1000 Core Design Based on MCNP Model in another window
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

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
Open the PDF for Numerical Investigation of Convective Heat Transfer to Supercritical Pressure Hydrogen in a Straight Tube in another window
Topics: Convection, Heat transfer, Hydrogen, Pressure, Simulation, Turbulence, Flow (Dynamics), Density, Temperature, Viscosity
Journal Articles

Parallel Analysis of Linear Systems in CORTH and KYLIN2

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
Open the PDF for Parallel Analysis of Linear Systems in CORTH and KYLIN2 in another window
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

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

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
Open the PDF for Mechanical Properties of Cubic (U,Zr)O 2 in another window
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

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
Open the PDF for Hydrogen–Air–Steam Deflagration Experiment Simulated Using Different Turbulent Flame-Speed Closure Models in another window
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

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
Open the PDF for Experimental Study on Melt Coolability Capability of Calandria Vault Water During Severe Accident in Indian PHWRs for Prolonged Duration in another window
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

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
Open the PDF for Method and Validation for Measurement of Effective Thermal Diffusivity and Conductivity of Pebble Bed in High Temperature Gas-Cooled Reactors in another window
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

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
Open the PDF for Analysis of Inertization Strategies for the Filtered Containment Venting System in Cofrentes Nuclear Power Plant in another window
Topics: Containment, Hydrogen, Nitrogen, Nuclear power stations, Oxygen, Risk, Combustion, Simulation
Journal Articles

Multiphysics Modeling of Pressurized Water Reactor Fuel Performance

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
Open the PDF for Multiphysics Modeling of Pressurized Water Reactor Fuel Performance in another window
Topics: Cladding systems (Building), Fuel rods, Fuels, Modeling, Nuclear fission, Temperature, Pressurized water reactors, Stress, Accidents