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Proceedings Papers

Enhanced Mechanical Properties of Iron-Chromium-Aluminum Cladding for Light Water Reactor Fuels

Raul B. Rebak, Evan J. Dolley, Wanming Zhang, Rajnikant V. Umretiya, Andrew K. Hoffman

Proc. ASME. PVP2022, Volume 4B: Materials and Fabrication, V04BT06A016, July 17–22, 2022

Paper No: PVP2022-80557

DOI: https://doi.org/10.1115/PVP2022-80557

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Topics: Aluminum, Cladding systems (Building), Creep, Fuels, Iron, Light water reactors, Mechanical properties

Proceedings Papers

Mitigating LWR IronClad Fuel Cladding Dissolution Using Zinc Water Chemistry

Raul B. Rebak, Liang Yin, Michael Larsen, Rajnikant V. Umretiya, Andrew K. Hoffman

Proc. ASME. PVP2022, Volume 4B: Materials and Fabrication, V04BT06A017, July 17–22, 2022

Paper No: PVP2022-80559

DOI: https://doi.org/10.1115/PVP2022-80559

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Topics: Cladding systems (Building), Corrosion, Fuels, Light water reactors, Water chemistry

Proceedings Papers

Fabrication and Mechanical Aspects of Using FeCrAl for Light Water Reactor Fuel Cladding

Raul B. Rebak, Shenyan Huang, Michael Schuster, Steve J. Buresh, Evan J. Dolley

Proc. ASME. PVP2019, Volume 6B: Materials and Fabrication, V06BT06A010, July 14–19, 2019

Paper No: PVP2019-93128

DOI: https://doi.org/10.1115/PVP2019-93128

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Topics: Cladding systems (Building), Fuels, Light water reactors, Manufacturing, Accidents, Alloys, Aluminum, Failure, Generation IV reactors, Iron

Proceedings Papers

Using Additive Manufacturing for Making Light Water Reactor Components

Raul B. Rebak, Xiaoyuan Lou

Proc. ASME. PVP2019, Volume 6B: Materials and Fabrication, V06BT06A011, July 14–19, 2019

Paper No: PVP2019-93129

DOI: https://doi.org/10.1115/PVP2019-93129

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Topics: Additive manufacturing, Light water reactors, Corrosion, Manufacturing, Cracking (Materials), Design, Electrochemical analysis, Failure mechanisms, Fracture (Process), Fuel rods

Proceedings Papers

FeCrAl Alloys for Accident Tolerant Fuel Cladding in Light Water Reactors

Raul B. Rebak, Kurt A. Terrani, Russ M. Fawcett

Proc. ASME. PVP2016, Volume 6B: Materials and Fabrication, V06BT06A009, July 17–21, 2016

Paper No: PVP2016-63162

DOI: https://doi.org/10.1115/PVP2016-63162

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Topics: Accidents, Alloys, Cladding systems (Building), Fuels, Light water reactors, Fuel systems, Manufacturing, Aluminum, Cooling, Design

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

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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

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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

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Topics: Accidents, Cladding systems (Building), Light water reactors, Nuclear fuels, Steel, Alloys, Fuels, Aluminum, Steam, Chemical kinetics

Proceedings Papers

Resistance of Ferritic Steels to Stress Corrosion Cracking in High Temperature Water

Raul B. Rebak

Proc. ASME. PVP2013, Volume 6A: Materials and Fabrication, V06AT06A085, July 14–18, 2013

Paper No: PVP2013-97352

DOI: https://doi.org/10.1115/PVP2013-97352

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Topics: High temperature, Steel, Stress corrosion cracking, Water, Boiling water reactors, Cracking (Materials), Fracture (Process), Irradiation (Radiation exposure), Pressurized water reactors, Crack propagation

Proceedings Papers

Assessing Residual Strains in Nuclear Power Reactor Internal Components Weld Mockups of Nickel Alloys Using EBSD

Michelle A. Othon, Martin M. Morra, Suguru Ooki, Raul B. Rebak

Proc. ASME. PVP2013, Volume 6B: Materials and Fabrication, V06BT06A067, July 14–18, 2013

Paper No: PVP2013-97350

DOI: https://doi.org/10.1115/PVP2013-97350

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Topics: Electron backscatter diffraction, Nickel alloys, Nuclear reactors, Cracking (Materials), Fracture (Process), Metals, Tension, Alloys, Chemistry, Cross section (Physics)

Proceedings Papers

Anodic Polarization Behavior of Titanium Grade 7 in Dust Deliquescence Salt Environments

Kenneth J. Evans, Raul B. Rebak

Proc. ASME. PVP2007, Volume 7: Operations, Applications and Components, 387-394, July 22–26, 2007

Paper No: PVP2007-26161

DOI: https://doi.org/10.1115/PVP2007-26161

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Topics: Corrosion, Deliquescence, Dust, Polarization (Electricity), Polarization (Light), Polarization (Waves), Titanium

Proceedings Papers

Enhanced Corrosion Resistance of Iron-Based Amorphous Alloys

Raul B. Rebak, S. Daniel Day, Tiangan Lian, Louis F. Aprigliano, Phillip D. Hailey, Joseph C. Farmer

Proc. ASME. PVP2007, Volume 7: Operations, Applications and Components, 433-441, July 22–26, 2007

Paper No: PVP2007-26166

DOI: https://doi.org/10.1115/PVP2007-26166

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Topics: Corrosion, Corrosion resistance, Iron, Metallic glasses, Testing

Proceedings Papers

Long-Term Corrosion Potential Behavior of Alloy 22 in Hot 5 m CaCl 2 + 5 m Ca(NO 3 ) 2 Brines

Marti´n A. Rodri´guez, Ricardo M. Carranza, Marshall L. Stuart, Raul B. Rebak

Proc. ASME. PVP2007, Volume 7: Operations, Applications and Components, 395-404, July 22–26, 2007

Paper No: PVP2007-26162

DOI: https://doi.org/10.1115/PVP2007-26162

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Topics: Alloys, Corrosion

Proceedings Papers

Long-Term Immersion Testing of Alloy 22 and Titanium Grade 7 Double U-Bend Specimens

Kenneth J. Evans, Marshall L. Stuart, Phillip D. Hailey, Raul B. Rebak

Proc. ASME. PVP2007, Volume 7: Operations, Applications and Components, 405-412, July 22–26, 2007

Paper No: PVP2007-26163

DOI: https://doi.org/10.1115/PVP2007-26163

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Topics: Alloys, Testing, Titanium, Water

Proceedings Papers

Crevice Repassivation Potential of Alloy 22 in High-Nitrate Dust Deliquescence Type Environments

Tiangan Lian, Gregory E. Gdowski, Phillip D. Hailey, Raul B. Rebak

Proc. ASME. PVP2007, Volume 7: Operations, Applications and Components, 413-423, July 22–26, 2007

Paper No: PVP2007-26164

DOI: https://doi.org/10.1115/PVP2007-26164

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Topics: Alloys, Deliquescence, Dust, Potassium, Sodium

Proceedings Papers

The Long-Term Corrosion Test Facility at Lawrence Livermore National Laboratory

David V. Fix, Raul B. Rebak

Proc. ASME. PVP2007, Volume 7: Operations, Applications and Components, 425-431, July 22–26, 2007

Paper No: PVP2007-26165

DOI: https://doi.org/10.1115/PVP2007-26165

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Topics: Corrosion, Test facilities, Weight (Mass)

Proceedings Papers

Effect of Chemistry Variations of Wrought N06022 Plates on the Repassivation Potential in 1 M NaCl at 90°C

Kevin G. Mon, Raul B. Rebak

Proc. ASME. PVP2008, Volume 7: Operations, Applications and Components, 201-208, July 27–31, 2008

Paper No: PVP2008-61269

DOI: https://doi.org/10.1115/PVP2008-61269

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Topics: ASTM International, Chemistry, Heat, Plates (structures), Alloys, Weight (Mass), Molybdenum, Nickel, Polarization (Electricity), Polarization (Light)

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

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Topics: Alloys, Cladding systems (Building), Containers, Corrosion, Corrosion resistance, Damage, Fuel rods, Fuels, Irradiation (Radiation exposure), Modeling

Journal Articles

Stifling of Crevice Corrosion in Alloy 22 During Constant Potential Tests

Raul B. Rebak

J. Pressure Vessel Technol. February 2009, 131(1): 014501.

DOI: https://doi.org/10.1115/1.2967883

Published Online: November 7, 2008

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Topics: Corrosion, Alloys

Proceedings Papers

Passive Corrosion Behavior of Alloy 22 in Multi-Ionic Aqueous Environments

Tiangan Lian, John C. Estill, Gary A. Hust, Dave V. Fix, Raul B. Rebak

Proc. ASME. PVP2002, Transportation, Storage, and Disposal of Radioactive Materials, 67-74, August 5–9, 2002

Paper No: PVP2002-1615

DOI: https://doi.org/10.1115/PVP2002-1615

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Topics: Alloys, Corrosion, Containers, Water, Weight (Mass), Corrosion resistance, Radioactive wastes

Journal citation

NARROW

Enhanced Mechanical Properties of Iron-Chromium-Aluminum Cladding for Light Water Reactor Fuels

Mitigating LWR IronClad Fuel Cladding Dissolution Using Zinc Water Chemistry

Fabrication and Mechanical Aspects of Using FeCrAl for Light Water Reactor Fuel Cladding

Using Additive Manufacturing for Making Light Water Reactor Components

FeCrAl Alloys for Accident Tolerant Fuel Cladding in Light Water Reactors

Hydrogen Diffusion in FeCrAl Alloys for Light Water Reactors Cladding Applications

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

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

Resistance of Ferritic Steels to Stress Corrosion Cracking in High Temperature Water

Assessing Residual Strains in Nuclear Power Reactor Internal Components Weld Mockups of Nickel Alloys Using EBSD

Anodic Polarization Behavior of Titanium Grade 7 in Dust Deliquescence Salt Environments

Enhanced Corrosion Resistance of Iron-Based Amorphous Alloys

Long-Term Corrosion Potential Behavior of Alloy 22 in Hot 5 m CaCl 2 + 5 m Ca(NO 3 ) 2 Brines

Long-Term Immersion Testing of Alloy 22 and Titanium Grade 7 Double U-Bend Specimens

Crevice Repassivation Potential of Alloy 22 in High-Nitrate Dust Deliquescence Type Environments

The Long-Term Corrosion Test Facility at Lawrence Livermore National Laboratory

Effect of Chemistry Variations of Wrought N06022 Plates on the Repassivation Potential in 1 M NaCl at 90°C

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

Stifling of Crevice Corrosion in Alloy 22 During Constant Potential Tests

Passive Corrosion Behavior of Alloy 22 in Multi-Ionic Aqueous Environments

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