1-19 of 19
Zirconium alloys
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
Proceedings Papers

Results and Correlations From Analyses of the ENSA ENUN 32P Cask Transport Tests

Elena A. Kalinina, Natalie Gordon, Douglas J. Ammerman, William L. Uncapher, Sylvia J. Saltzstein, Catherine Wright
Proc. ASME. PVP2018, Volume 7: Operations, Applications, and Components, V007T07A040, July 15–20, 2018
Paper No: PVP2018-84763
DOI: https://doi.org/10.1115/PVP2018-84763
View Paper titled, Results and Correlations From Analyses of the ENSA ENUN 32P Cask Transport Tests
Click here to open pdf in another window PDF for Results and Correlations From Analyses of the ENSA ENUN 32P Cask Transport Tests
Topics: Accelerometers, Collaboration, Failure, Modeling, Railroads, Rails, Roads, Seas, Ships, Shock (Mechanics)
Proceedings Papers

Pilot Study for Uncertainty Analysis in Probabilistic Fitness-for-Service Evaluations of Zr-2.5Nb Pressure Tubes: Identification of Influential Variables

Christopher Manu, Suresh Datla, Leonid Gutkin
Proc. ASME. PVP2018, Volume 1B: Codes and Standards, V01BT01A076, July 15–20, 2018
Paper No: PVP2018-85010
DOI: https://doi.org/10.1115/PVP2018-85010
View Paper titled, Pilot Study for Uncertainty Analysis in Probabilistic Fitness-for-Service Evaluations of Zr-2.5Nb Pressure Tubes: Identification of Influential Variables
Click here to open pdf in another window PDF for Pilot Study for Uncertainty Analysis in Probabilistic Fitness-for-Service Evaluations of Zr-2.5Nb Pressure Tubes: Identification of Influential Variables
Topics: Fitness-for-service, Pressure, Uncertainty analysis, Zirconium, Leak-before-break, Uncertainty, Fracture (Materials), Sensitivity analysis, Computer software, Computers
Proceedings Papers

Pilot Study for Uncertainty Analysis in Probabilistic Fitness-for-Service Evaluations of Zr-2.5Nb Pressure Tubes: Uncertainty Characterization

Leonid Gutkin, Suresh Datla, Christopher Manu
Proc. ASME. PVP2018, Volume 1B: Codes and Standards, V01BT01A077, July 15–20, 2018
Paper No: PVP2018-85011
DOI: https://doi.org/10.1115/PVP2018-85011
View Paper titled, Pilot Study for Uncertainty Analysis in Probabilistic Fitness-for-Service Evaluations of Zr-2.5Nb Pressure Tubes: Uncertainty Characterization
Click here to open pdf in another window PDF for Pilot Study for Uncertainty Analysis in Probabilistic Fitness-for-Service Evaluations of Zr-2.5Nb Pressure Tubes: Uncertainty Characterization
Topics: Fitness-for-service, Pressure, Uncertainty, Uncertainty analysis, Zirconium, Computer software, Leak-before-break, Design, Fracture (Materials), Nuclear power stations
Proceedings Papers

Multiscale Stress-Diffusion Analysis of Notch-Tip Hydrogen Profiles in Zircaloy-4

Said El Chamaa, Mitesh Patel, Mark R. Wenman, Catrin M. Davies
Proc. ASME. PVP2018, Volume 6B: Materials and Fabrication, V06BT06A013, July 15–20, 2018
Paper No: PVP2018-84555
DOI: https://doi.org/10.1115/PVP2018-84555
View Paper titled, Multiscale Stress-Diffusion Analysis of Notch-Tip Hydrogen Profiles in Zircaloy-4
Click here to open pdf in another window PDF for Multiscale Stress-Diffusion Analysis of Notch-Tip Hydrogen Profiles in Zircaloy-4
Topics: Diffusion (Physics), Hydrogen, Stress, Anisotropy, Stress analysis (Engineering), Crystals, Dipoles (Electromagnetism), Finite element analysis, Modeling, Nuclear industry
Proceedings Papers

Comparison of Various Damage Models in Modelling 3D Crack Propagation

Bruce W. Williams, C. Hari M. Simha
Proc. ASME. PVP2016, Volume 6A: Materials and Fabrication, V06AT06A001, July 17–21, 2016
Paper No: PVP2016-63082
DOI: https://doi.org/10.1115/PVP2016-63082
View Paper titled, Comparison of Various Damage Models in Modelling 3D Crack Propagation
Click here to open pdf in another window PDF for Comparison of Various Damage Models in Modelling 3D Crack Propagation
Topics: Crack propagation, Damage, Modeling, Fracture (Materials), Zirconium, Pipelines, Pressure, Steel, Anisotropy, Engineering simulation
Proceedings Papers

Use of the Extended Finite Element Method in the Assessment of Delayed Hydride Cracking

Martin Booth, Michael Martin
Proc. ASME. PVP2016, Volume 1A: Codes and Standards, V01AT01A051, July 17–21, 2016
Paper No: PVP2016-63156
DOI: https://doi.org/10.1115/PVP2016-63156
View Paper titled, Use of the Extended Finite Element Method in the Assessment of Delayed Hydride Cracking
Click here to open pdf in another window PDF for Use of the Extended Finite Element Method in the Assessment of Delayed Hydride Cracking
Topics: Cracking (Materials), Finite element methods, Fracture (Process), Stress, Zirconium, Zirconium alloys, Hydrogen, Water, Brittleness, Corrosion
Proceedings Papers

Measurement of Hydride Precipitation and Dissolution Kinetics Using Synchrotron X-Rays

Oksana Shiman, Eric Tulk, Mark R. Daymond
Proc. ASME. PVP2016, Volume 1A: Codes and Standards, V01AT01A052, July 17–21, 2016
Paper No: PVP2016-63729
DOI: https://doi.org/10.1115/PVP2016-63729
View Paper titled, Measurement of Hydride Precipitation and Dissolution Kinetics Using Synchrotron X-Rays
Click here to open pdf in another window PDF for Measurement of Hydride Precipitation and Dissolution Kinetics Using Synchrotron X-Rays
Topics: Precipitation, X-rays, Hydrogen, Zirconium, Anisotropy, Cracking (Materials), Failure, Fracture (Materials), Fracture (Process), Fracture toughness
Proceedings Papers

Validation of Weight Function Based Process-Zone Model for Evaluation of Delayed Hydride Cracking Initiation in Zr-2.5Nb Pressure Tubes

Steven X. Xu, Dennis Kawa, Jun Cui, Heather Chaput
Proc. ASME. PVP2016, Volume 1A: Codes and Standards, V01AT01A054, July 17–21, 2016
Paper No: PVP2016-64024
DOI: https://doi.org/10.1115/PVP2016-64024
View Paper titled, Validation of Weight Function Based Process-Zone Model for Evaluation of Delayed Hydride Cracking Initiation in Zr-2.5Nb Pressure Tubes
Click here to open pdf in another window PDF for Validation of Weight Function Based Process-Zone Model for Evaluation of Delayed Hydride Cracking Initiation in Zr-2.5Nb Pressure Tubes
Topics: Fracture (Process), Pressure, Weight (Mass), Zirconium, Fracture (Materials), Fuels, Atoms, Bearings, Corrosion, Diffusion (Physics)
Proceedings Papers

Regulatory Perspective for the Definition of Probabilistic Acceptance Criteria for CANDU Pressure Tubes

Sankar Laxman, Blair Carroll, John Jin
Proc. ASME. PVP2016, Volume 1B: Codes and Standards, V01BT01A020, July 17–21, 2016
Paper No: PVP2016-63655
DOI: https://doi.org/10.1115/PVP2016-63655
View Paper titled, Regulatory Perspective for the Definition of Probabilistic Acceptance Criteria for CANDU Pressure Tubes
Click here to open pdf in another window PDF for Regulatory Perspective for the Definition of Probabilistic Acceptance Criteria for CANDU Pressure Tubes
Topics: Acceptance criteria, Pressure, Failure, Fitness-for-service, Risk assessment, Safety, Zirconium alloys
Proceedings Papers

Hydrogen Diffusion in FeCrAl Alloys for Light Water Reactors Cladding Applications

Raul B. Rebak, Young-Jin Kim
Proc. ASME. PVP2016, Volume 6B: Materials and Fabrication, V06BT06A010, July 17–21, 2016
Paper No: PVP2016-63164
DOI: https://doi.org/10.1115/PVP2016-63164
View Paper titled, Hydrogen Diffusion in FeCrAl Alloys for Light Water Reactors Cladding Applications
Click here to open pdf in another window PDF for Hydrogen Diffusion in FeCrAl Alloys for Light Water Reactors Cladding Applications
Topics: Alloys, Cladding systems (Building), Diffusion (Physics), Hydrogen, Light water reactors, Coolants, Fuels, Zirconium alloys, Accidents, Aluminum
Proceedings Papers

Anticipated Improved Performance of Advanced Steel Cladding Under Long Term Dry Storage of Spent Fuel

Raul B. Rebak, Shenyan Huang
Proc. ASME. PVP2015, Volume 7: Operations, Applications and Components, V007T07A042, July 19–23, 2015
Paper No: PVP2015-45643
DOI: https://doi.org/10.1115/PVP2015-45643
View Paper titled, Anticipated Improved Performance of Advanced Steel Cladding Under Long Term Dry Storage of Spent Fuel
Click here to open pdf in another window PDF for Anticipated Improved Performance of Advanced Steel Cladding Under Long Term Dry Storage of Spent Fuel
Topics: Cladding systems (Building), Spent nuclear fuels, Steel, Storage, Fuels, Zirconium alloys, Accidents, Alloys, Delays, Fuel rods
Proceedings Papers

Characterization of Advanced Steels as Accident Tolerant Cladding for Light Water Reactor Nuclear Fuel

Raul B. Rebak
Proc. ASME. PVP2015, Volume 6B: Materials and Fabrication, V06BT06A006, July 19–23, 2015
Paper No: PVP2015-45652
DOI: https://doi.org/10.1115/PVP2015-45652
View Paper titled, Characterization of Advanced Steels as Accident Tolerant Cladding for Light Water Reactor Nuclear Fuel
Click here to open pdf in another window PDF for Characterization of Advanced Steels as Accident Tolerant Cladding for Light Water Reactor Nuclear Fuel
Topics: Accidents, Cladding systems (Building), Light water reactors, Nuclear fuels, Steel, Alloys, Fuels, Aluminum, Steam, Chemical kinetics
Proceedings Papers

A Comparison of Finite Element Cohesive-Zone Modelling With the Process-Zone Approach for the Prediction of Delayed Hydride Cracking

Michael Martin
Proc. ASME. PVP2013, Volume 6A: Materials and Fabrication, V06AT06A004, July 14–18, 2013
Paper No: PVP2013-97077
DOI: https://doi.org/10.1115/PVP2013-97077
View Paper titled, A Comparison of Finite Element Cohesive-Zone Modelling With the Process-Zone Approach for the Prediction of Delayed Hydride Cracking
Click here to open pdf in another window PDF for A Comparison of Finite Element Cohesive-Zone Modelling With the Process-Zone Approach for the Prediction of Delayed Hydride Cracking
Topics: Cracking (Materials), Finite element analysis, Fracture (Process), Modeling, Stress, Fracture (Materials), Water, Zirconium alloys, Corrosion, Damage
Proceedings Papers

Modeling of In-Situ Hydride Growth in Zr-2.5%Nb

Feng Xu, Don Metzger
Proc. ASME. PVP2011, Volume 6: Materials and Fabrication, Parts A and B, 1371-1375, July 17–21, 2011
Paper No: PVP2011-58059
DOI: https://doi.org/10.1115/PVP2011-58059
View Paper titled, Modeling of In-Situ Hydride Growth in Zr-2.5%Nb
Click here to open pdf in another window PDF for Modeling of In-Situ Hydride Growth in Zr-2.5%Nb
Topics: Modeling, Zirconium, Diffusion (Physics), Stress, Creep, Ductility, Finite element analysis, Fracture (Materials), Fracture toughness, Hydrostatics
Proceedings Papers

Presentation of the Afcen RCC-MRx Code for Sodium Reactors (SFR), Research Reactors (RR) and Fusion (ITER): General Overview

T. Lebarbe´, S. Marie, B. Drubay, O. Gelineau, D. Bonne, Frantz De La Burgade
Proc. ASME. PVP2010, ASME 2010 Pressure Vessels and Piping Conference: Volume 1, 797-802, July 18–22, 2010
Paper No: PVP2010-25673
DOI: https://doi.org/10.1115/PVP2010-25673
View Paper titled, Presentation of the Afcen RCC-MRx Code for Sodium Reactors (SFR), Research Reactors (RR) and Fusion (ITER): General Overview
Click here to open pdf in another window PDF for Presentation of the Afcen RCC-MRx Code for Sodium Reactors (SFR), Research Reactors (RR) and Fusion (ITER): General Overview
Topics: Aluminum alloys, Construction, Design, High temperature, Irradiation (Radiation exposure), Materials properties, Sodium, Sodium fast reactors, Zirconium alloys
Proceedings Papers

The Long-Term Environmental Degradation of Zirconium Alloys in Contact With Spent Nuclear Fuel: A Review

Raul B. Rebak
Proc. ASME. PVP2008, Volume 7: Operations, Applications and Components, 209-214, July 27–31, 2008
Paper No: PVP2008-61272
DOI: https://doi.org/10.1115/PVP2008-61272
View Paper titled, The Long-Term Environmental Degradation of Zirconium Alloys in Contact With Spent Nuclear Fuel: A Review
Click here to open pdf in another window PDF for The Long-Term Environmental Degradation of Zirconium Alloys in Contact With Spent Nuclear Fuel: A Review
Topics: Alloys, Cladding systems (Building), Containers, Corrosion, Corrosion resistance, Damage, Fuel rods, Fuels, Irradiation (Radiation exposure), Modeling
Proceedings Papers

The Effect of Plasticity on Process-Zone Predictions of DHC Initiation at a Flaw in CANDU Reactor Zr-Nb Pressure Tubes

Douglas A. Scarth, Ted Smith
Proc. ASME. PVP2002, Service Experience and Failure Assessment Applications, 19-30, August 5–9, 2002
Paper No: PVP2002-1171
DOI: https://doi.org/10.1115/PVP2002-1171
View Paper titled, The Effect of Plasticity on Process-Zone Predictions of DHC Initiation at a Flaw in CANDU Reactor Zr-Nb Pressure Tubes
Click here to open pdf in another window PDF for The Effect of Plasticity on Process-Zone Predictions of DHC Initiation at a Flaw in CANDU Reactor Zr-Nb Pressure Tubes
Topics: Plasticity, Pressure, Zirconium, Fracture (Materials), Fracture (Process), Zirconium alloys, Atoms, Diffusion (Physics), Geometry, Hydrogen
Proceedings Papers

Postirradiation Ductility Demonstration Tests of Weapons-Derived MOX Fuel Cladding

W. J. McAfee, W. R. Hendrich, T. E. McGreevy, C. A. Baldwin, N. H. Packan
Proc. ASME. PVP2004, Flaw Evaluation, Service Experience, and Materials for Hydrogen Service, 213-220, July 25–29, 2004
Paper No: PVP2004-2561
DOI: https://doi.org/10.1115/PVP2004-2561
View Paper titled, Postirradiation Ductility Demonstration Tests of Weapons-Derived MOX Fuel Cladding
Click here to open pdf in another window PDF for Postirradiation Ductility Demonstration Tests of Weapons-Derived MOX Fuel Cladding
Topics: Cladding systems (Building), Ductility, Fuels, Weapons, Irradiation (Radiation exposure), Gallium, Temperature, Tensile strength, Uranium, Zirconium
Proceedings Papers

Overview of Computational Methods for Hydrogen Diffusion Coupled With Stress and Temperature Gradients in Zirconium Reactor Components

Don R. Metzger, Richard G. Sauve´, Tom P. Byrne
Proc. ASME. PVP2006-ICPVT-11, Volume 2: Computer Technology, 477-484, July 23–27, 2006
Paper No: PVP2006-ICPVT-11-93664
DOI: https://doi.org/10.1115/PVP2006-ICPVT-11-93664
View Paper titled, Overview of Computational Methods for Hydrogen Diffusion Coupled With Stress and Temperature Gradients in Zirconium Reactor Components
Click here to open pdf in another window PDF for Overview of Computational Methods for Hydrogen Diffusion Coupled With Stress and Temperature Gradients in Zirconium Reactor Components
Topics: Computational methods, Diffusion (Physics), Hydrogen, Stress, Temperature gradient, Zirconium, Cracking (Materials), Fracture (Process), Fuels, Temperature