1-20 of 43
Cladding systems (Building)
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

Revenue Requirements Method for Assessing the Cost Impact of Fuel Cladding Corrosion in a Supercritical Water-Cooled Small Modular Reactor: A Methodological Review on Life Cycle Costing Corrosion

Alberto D'Ansi Mendoza España
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Review Articles
ASME J of Nuclear Rad Sci. October 2024, 10(4): 040801.
Paper No: NERS-23-1077
https://doi.org/10.1115/1.4064639
Published Online: May 10, 2024
View Article titled, Revenue Requirements Method for Assessing the Cost Impact of Fuel Cladding Corrosion in a Supercritical Water-Cooled Small Modular Reactor: A Methodological Review on Life Cycle Costing Corrosion
Open the PDF for Revenue Requirements Method for Assessing the Cost Impact of Fuel Cladding Corrosion in a Supercritical Water-Cooled Small Modular Reactor: A Methodological Review on Life Cycle Costing Corrosion in another window
Topics: Cladding systems (Building), Corrosion, Fuels, Supercritical water reactors, Water
Journal Articles

Thermomechanical Performance Assessment of U-Mo Monolithic Fuel Plates With Zircaloy Cladding

Hakan Ozaltun, James I. Cole, Barry H. Rabin
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2024, 10(2): 021601.
Paper No: NERS-23-1048
https://doi.org/10.1115/1.4063163
Published Online: November 1, 2023
View Article titled, Thermomechanical Performance Assessment of U-Mo Monolithic Fuel Plates With Zircaloy Cladding
Open the PDF for Thermomechanical Performance Assessment of U-Mo Monolithic Fuel Plates With Zircaloy Cladding in another window
Topics: Cladding systems (Building), Fuels, Stress, Temperature, Irradiation (Radiation exposure), Plates (structures), Deformation
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
Open the PDF for Uncertainty and Sensitivity Evaluation of the QUENCH-02 Experiment Simulation Using the ASYST Code in another window
Topics: Cladding systems (Building), Electricity (Physics), Flow (Dynamics), Hydrogen, Oxidation, Steam, Temperature, Uncertainty, Water, Boundary-value problems
Journal Articles

Preliminary Analysis of Reactivity Feedbacks for Inner-Side Chromium Coating

Rofida Hamad Khlifa, Nicolay N. Nikitenkov
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2023, 9(1): 012003.
Paper No: NERS-22-1044
https://doi.org/10.1115/1.4055012
Published Online: September 1, 2022
View Article titled, Preliminary Analysis of Reactivity Feedbacks for Inner-Side Chromium Coating
Open the PDF for Preliminary Analysis of Reactivity Feedbacks for Inner-Side Chromium Coating in another window
Topics: Boron, Coatings, Fuels, Temperature, Cladding systems (Building), Neutrons, Accidents
Journal Articles

Fuel Performance Modeling at High Burn-Up by FEMAXI-6 Code

Jakub Lüley, Branislav Vrban, Štefan Čerba, Filip Osuský, 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): 041601.
Paper No: NERS-21-1030
https://doi.org/10.1115/1.4052519
Published Online: March 22, 2022
View Article titled, Fuel Performance Modeling at High Burn-Up by FEMAXI-6 Code
Open the PDF for Fuel Performance Modeling at High Burn-Up by FEMAXI-6 Code in another window
Topics: Fuels, Grain size, Irradiation (Radiation exposure), Modeling, Nuclear fission, Rods, Pressure, Cladding systems (Building), Stress
Journal Articles

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

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 Article titled, 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

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

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

Superphénix Benchmark Part I: Results of Static Neutronics

Alexander Ponomarev, Konstantin Mikityuk, Liang Zhang, Evgeny Nikitin, Emil Fridman, Francisco Álvarez-Velarde, Pablo Romojaro Otero, Antonio Jiménez-Carrascosa, Nuria García-Herranz, Ben Lindley, Una Baker, Armin Seubert, Romain Henry
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2022, 8(1): 011320.
Paper No: NERS-21-1046
https://doi.org/10.1115/1.4051449
Published Online: October 8, 2021
View Article titled, Superphénix Benchmark Part I: Results of Static Neutronics
Open the PDF for Superphénix Benchmark Part I: Results of Static Neutronics in another window
Topics: Density, Fuels, Rods, Sodium, Temperature, Steel, Geometry, Cladding systems (Building), Neutrons, Chemical kinetics
Journal Articles

GTAW Welded Inconel 625 Alloy Fuel Cladding for the Canadian SCWR: Microstructure and Mechanical Property Characterization

Cota-Sanchez German, Xiao Lin
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2021, 7(3): 031304.
Paper No: NERS-20-1053
https://doi.org/10.1115/1.4049278
Published Online: March 16, 2021
View Article titled, GTAW Welded Inconel 625 Alloy Fuel Cladding for the Canadian SCWR: Microstructure and Mechanical Property Characterization
Open the PDF for GTAW Welded Inconel 625 Alloy Fuel Cladding for the Canadian SCWR: Microstructure and Mechanical Property Characterization in another window
Topics: Heat, Welding, Cladding systems (Building), Fuels, Alloys, Supercritical water reactors, Mechanical properties, Gas tungsten arc welding, Welded joints
Journal Articles

Microstructure and Nanoindentation Studies of Hydridated Zircaloy-4 Claddings After High Temperature Oxidation

Petra Gávelová, Patricie Halodová, Daniela Marušáková, Ondřej Libera, Jakub Krejčí, Věra Vrtílková
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2021, 7(2): 021604.
Paper No: NERS-20-1110
https://doi.org/10.1115/1.4049053
Published Online: December 14, 2020
View Article titled, Microstructure and Nanoindentation Studies of Hydridated Zircaloy-4 Claddings After High Temperature Oxidation
Open the PDF for Microstructure and Nanoindentation Studies of Hydridated Zircaloy-4 Claddings After High Temperature Oxidation in another window
Topics: Cladding systems (Building), High temperature, Hydrogen, Nanoindentation, Oxidation, Oxygen, Temperature, Zirconium, Accidents
Journal Articles

On Debris-Fretting Impact—The Study of Oxide and Chromium Layer Application

Marcin Kopeć, Ondřej Pašta, Martina Malá, Patricie Halodová, Ladislav Cvrček, Jakub Krejčí
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2021, 7(2): 021802.
Paper No: NERS-20-1093
https://doi.org/10.1115/1.4048239
Published Online: November 16, 2020
View Article titled, On Debris-Fretting Impact—The Study of Oxide and Chromium Layer Application
Open the PDF for On Debris-Fretting Impact—The Study of Oxide and Chromium Layer Application in another window
Topics: Cladding systems (Building), Coatings, Fuels, Testing, Wear, Wire, Zirconium, Failure, X-rays, Focused ion beams
Journal Articles

Analysis of Heat Transfer Characteristics of Canadian SCWR Fuel Assembly Concept

A. Nava Domínguez, Y. F. Rao, T. Beuthe
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2020, 6(3): 031114.
Paper No: NERS-19-1083
https://doi.org/10.1115/1.4046843
Published Online: June 5, 2020
View Article titled, Analysis of Heat Transfer Characteristics of Canadian SCWR Fuel Assembly Concept
Open the PDF for Analysis of Heat Transfer Characteristics of Canadian SCWR Fuel Assembly Concept in another window
Topics: Cladding systems (Building), Coolants, Flow (Dynamics), Fuels, Heat losses, Heat transfer, Manufacturing, Supercritical water reactors, Temperature, Modeling
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
Open the PDF for About the Thermal Hydraulic Analysis Part of a Coupled Study on a Thorium-Fueled SCWR Concept in another window
Topics: Computational fluid dynamics, Flow (Dynamics), Fluids, Fuels, Manufacturing, Supercritical water reactors, Temperature, Fuel rods, Boundary-value problems, Wire
Journal Articles

Postoperation Dose Rate Estimates for the Very-Small, Long-Life, Modular Reactor

Luis M. Palomino, Mohamed S. El-Genk, Timothy M. Schriener
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2020, 6(3): 031302.
Paper No: NERS-19-1045
https://doi.org/10.1115/1.4045297
Published Online: March 9, 2020
View Article titled, Postoperation Dose Rate Estimates for the Very-Small, Long-Life, Modular Reactor
Open the PDF for Postoperation Dose Rate Estimates for the Very-Small, Long-Life, Modular Reactor in another window
Topics: Cladding systems (Building), Emissions, Fuels, Neutrons, Photons, Steel, Vessels, Storage, Radioactivity, Isotopes
Journal Articles

Evaluation of Radiation Effects on Residents Living Around the NSRR Under External Hazards

Yuiko Motome, Yoshiya Akiyama, Hiroyuki Murao
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2020, 6(2): 021115.
Paper No: NERS-19-1073
https://doi.org/10.1115/1.4045075
Published Online: February 3, 2020
View Article titled, Evaluation of Radiation Effects on Residents Living Around the NSRR Under External Hazards
Open the PDF for Evaluation of Radiation Effects on Residents Living Around the NSRR Under External Hazards in another window
Topics: Earthquakes, Fuel rods, Fuel storage, Fuels, Radiation (Physics), Safety, Spent fuel storage, Tsunamis, Nuclear fission, Shapes
Journal Articles

From Micro to Nano: Material Characterization Methods for Testing of Nuclear Core and Structural Materials

Petra Gávelová, Patricie Halodová, Hygreeva Kiran Namburi, Iveta Adéla Prokůpková, Marek Mikloš, Jakub Krejčí
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2019, 5(3): 030917.
Paper No: NERS-18-1017
https://doi.org/10.1115/1.4043462
Published Online: May 3, 2019
View Article titled, From Micro to Nano: Material Characterization Methods for Testing of Nuclear Core and Structural Materials
Open the PDF for From Micro to Nano: Material Characterization Methods for Testing of Nuclear Core and Structural Materials in another window
Topics: Alloys, High temperature, Oxidation, Testing, Transparency, Zirconium, Creep, Microscopy, Electron backscatter diffraction, Cladding systems (Building)
Journal Articles

Thermomechanical Safety Analyses for a 238 Pu Production Target at the HFIR

Christopher J. Hurt, James D. Freels, Prashant K. Jain, G. Ivan Maldonado
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2019, 5(2): 021004.
Paper No: NERS-16-1070
https://doi.org/10.1115/1.4041295
Published Online: March 15, 2019
View Article titled, Thermomechanical Safety Analyses for a 238 Pu Production Target at the HFIR
Open the PDF for Thermomechanical Safety Analyses for a 238 Pu Production Target at the HFIR in another window
Topics: Cycles, Irradiation (Radiation exposure), Safety, Temperature, Stress, Heat transfer, Electrical conductance, Steady state, Heat, Cladding systems (Building)
Journal Articles

Simulation of Nuclear Fuel Behavior in Accident Conditions With the DIONISIO Code

Martín Lemes, Alicia Denis, Alejandro Soba
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2019, 5(2): 020903.
Paper No: NERS-18-1078
https://doi.org/10.1115/1.4042705
Published Online: March 15, 2019
View Article titled, Simulation of Nuclear Fuel Behavior in Accident Conditions With the DIONISIO Code
Open the PDF for Simulation of Nuclear Fuel Behavior in Accident Conditions With the DIONISIO Code in another window
Topics: Accidents, Cladding systems (Building), Coolants, Fuel rods, Fuels, High temperature, Hydrogen, Simulation, Temperature, Water
Journal Articles

Implementation of Hydrogen Solid Solubility Data and Precipitation Threshold Stresses in the Fuel Rod Code TESPA-ROD

Felix Boldt
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2019, 5(2): 020904.
Paper No: NERS-18-1065
https://doi.org/10.1115/1.4042118
Published Online: March 15, 2019
View Article titled, Implementation of Hydrogen Solid Solubility Data and Precipitation Threshold Stresses in the Fuel Rod Code TESPA-ROD
Open the PDF for Implementation of Hydrogen Solid Solubility Data and Precipitation Threshold Stresses in the Fuel Rod Code TESPA-ROD in another window
Topics: Cladding systems (Building), Fuel rods, Heat, Hydrogen, Precipitation, Storage, Stress, Temperature, Transients (Dynamics), Simulation