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Proceedings Papers

Nickel Cladded Structural Components for Advanced Reactors

B. Barua, M. C. Messner, T.-L. Sham

Proc. ASME. PVP2022, Volume 1: Codes and Standards, V001T01A063, July 17–22, 2022

Paper No: PVP2022-84811

DOI: https://doi.org/10.1115/PVP2022-84811

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Topics: Nickel, Structural elements (Construction), Design, Creep, Fatigue, High temperature, ASME Standards, Corrosion, Molten salt reactors, Base metals

Proceedings Papers

Further Developments in Nuclear Pressure Vessel Manufacture Using the Hot Isostatic Pressing Process and Thick-Section Electron Beam Welding

Ted Warner, John Sulley, Phil Wallace, David Stewart, Gary Jones, Dan Thatcher

Proc. ASME. PVP2022, Volume 4A: Materials and Fabrication, V04AT06A004, July 17–22, 2022

Paper No: PVP2022-79403

DOI: https://doi.org/10.1115/PVP2022-79403

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Topics: Alloy steel, Cladding systems (Building), Electron beam welding, Hot pressing, Oxygen, Powder metallurgy, Pressure vessels, Reactor vessels

Proceedings Papers

Post-Irradiation Fracture Toughness Characterization of Generation II FeCrAl Alloys

Xiang (Frank) Chen, Kevin G. Field, Richard Howard, Caleb P. Massey, Andrew T. Nelson

Proc. ASME. PVP2022, Volume 4B: Materials and Fabrication, V04BT06A019, July 17–22, 2022

Paper No: PVP2022-84517

DOI: https://doi.org/10.1115/PVP2022-84517

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Topics: Accidents, Alloys, Cladding systems (Building), Embrittlement, Fracture toughness, Fuels, Hardening, Irradiation (Radiation exposure)

Proceedings Papers

DetaClad™ Characterization for High-Temperature and High-Pressure Hydrogen Service

Olivier Sarrat, Curtis Prothe, Tim Delahanty

Proc. ASME. PVP2022, Volume 4B: Materials and Fabrication, V04BT06A022, July 17–22, 2022

Paper No: PVP2022-80639

DOI: https://doi.org/10.1115/PVP2022-80639

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Topics: Corrosion, High pressure (Physics), High temperature, Hydrogen, Cladding systems (Building), Pressure vessels, Alloys, Bond strength, Carbon steel, Damage

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

Large-Scale Parametric Modeling of Spent Nuclear Fuel Dynamics in the 30 cm Package Drop Scenario

Kevin Kadooka, James Fitzpatrick, Nicholas Klymyshyn

Proc. ASME. PVP2022, Volume 5: Operations, Applications, and Components; Seismic Engineering; ASME Nondestructive Evaluation, Diagnosis and Prognosis (NDPD) Division, V005T07A030, July 17–22, 2022

Paper No: PVP2022-84747

DOI: https://doi.org/10.1115/PVP2022-84747

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Topics: Dynamics (Mechanics), Modeling, Spent nuclear fuels, Fuels, Manufacturing, Simulation, Stress, Boiling water reactors, Cladding systems (Building), Fuel rods

Proceedings Papers

Finite Element Analysis of Ring Compression Testing for Used Nuclear Fuel Cladding

Zenghu Han, Michael C. Billone, Yung Y. Liu

Paper No: PVP2022-83911

DOI: https://doi.org/10.1115/PVP2022-83911

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Topics: Cladding systems (Building), Compression, Finite element analysis, Nuclear fuels, Testing, Storage, Transportation systems, Ductility, Fuels, Mechanical properties

Proceedings Papers

Effect of Plastic Constraint and Cladding on Semi-Elliptical Shaped Crack in Fracture Toughness Evaluation for a Reactor Pressure Vessel Steel

Masaki Shimodaira, Tohru Tobita, Yasuto Nagoshi, Kai Lu, Jinya Katsuyama

Proc. ASME. PVP2021, Volume 1: Codes and Standards, V001T01A057, July 13–15, 2021

Paper No: PVP2021-61725

DOI: https://doi.org/10.1115/PVP2021-61725

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Topics: Cladding systems (Building), Fracture (Materials), Fracture toughness, Reactor vessels, Steel

Proceedings Papers

30 CM Horizontal Drop of a Surrogate 17x17 PWR Fuel Assembly

Elena Kalinina, Doug Ammerman, Carissa Grey, Gregg Flores, Lucas Lujan, Sylvia Saltzstein, Danielle Michel

Proc. ASME. PVP2021, Volume 5: Operations, Applications, and Components; Seismic Engineering; Non-Destructive Examination, V005T07A022, July 13–15, 2021

Paper No: PVP2021-60533

DOI: https://doi.org/10.1115/PVP2021-60533

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Topics: Cladding systems (Building), Fuels, Manufacturing, Pressure, Pressurized water reactors, Spent nuclear fuels, Stress-strain curves, Arches, Bending (Stress), Blanks

Proceedings Papers

Thermal Analysis Evaluations Using the Dry Cask Simulator

S. R. Suffield, D. J. Richmond, J. A. Fort

Proc. ASME. PVP2021, Volume 5: Operations, Applications, and Components; Seismic Engineering; Non-Destructive Examination, V005T07A028, July 13–15, 2021

Paper No: PVP2021-61846

DOI: https://doi.org/10.1115/PVP2021-61846

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Topics: Thermal analysis, Fuels, Manufacturing, Computational fluid dynamics, Storage, Cladding systems (Building), Geometry, Heat, Stress, Temperature

Proceedings Papers

Structural Dynamics Modeling of Spent Nuclear Fuel During Hypothetical Package Drop Events

Kevin Kadooka, James Fitzpatrick, Nicholas Klymyshyn

Proc. ASME. PVP2021, Volume 5: Operations, Applications, and Components; Seismic Engineering; Non-Destructive Examination, V005T07A025, July 13–15, 2021

Paper No: PVP2021-61610

DOI: https://doi.org/10.1115/PVP2021-61610

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Topics: Modeling, Spent nuclear fuels, Structural dynamics, Fuels, Shock (Mechanics), Transportation systems, Boundary element methods, Buckling, Cladding systems (Building), Design

Proceedings Papers

Welding Tube to Tubesheet Joints for Corrosion Resisting Applications

Haresh K. Sippy

Proc. ASME. PVP2021, Volume 4: Materials and Fabrication, V004T06A004, July 13–15, 2021

Paper No: PVP2021-60974

DOI: https://doi.org/10.1115/PVP2021-60974

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Topics: Corrosion, Welding, Heat exchangers, Manufacturing, Shells, Stainless steel, Reliability, Base metals, Carbon steel, Cladding systems (Building)

Proceedings Papers

A52M/SA502 Dissimilar Metal RPV Repair Weld: Evaluation of Different Techniques

Heikki Keinänen, Pekka Nevasmaa, Juha Kuutti, Caitlin Huotilainen, Iikka Virkkunen, Mikko Peltonen, Henrik Sirén

Proc. ASME. PVP2020, Volume 6: Materials and Fabrication, V006T06A109, August 3, 2020

Paper No: PVP2020-21233

DOI: https://doi.org/10.1115/PVP2020-21233

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Topics: Maintenance, Metals, Welding, Cladding systems (Building), Alloys, Reactor vessels, Steel, Filler metals, Heat treating (Metalworking), Nickel

Proceedings Papers

A52M/SA52 Dissimilar Metal RPV Repair Weld: Experimental Evaluation and Post-Weld Characterizations

Iikka Virkkunen, Mikko Peltonen, Henrik Sirén, Pekka Nevasmaa, Caitlin Huotilainen, Heikki Keinänen, Juha Kuutti, Aloshious Lambai, Gaurav Mohanty, Mari Honkanen

Proc. ASME. PVP2020, Volume 6: Materials and Fabrication, V006T06A110, August 3, 2020

Paper No: PVP2020-21236

DOI: https://doi.org/10.1115/PVP2020-21236

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Topics: Maintenance, Metals, Welding, Cracking (Materials), Fracture (Process), Reactor vessels, Alloys, Fracture (Materials), Heat, Alloy steel

Proceedings Papers

Application of Nickel Electroplating for PWR Reactor Pressure Vessel Cladding Repair

Seong Sik Hwang, Dong Jin Kim

Proc. ASME. PVP2020, Volume 1: Codes and Standards, V001T01A001, August 3, 2020

Paper No: PVP2020-21051

DOI: https://doi.org/10.1115/PVP2020-21051

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Topics: Alloys, Cladding systems (Building), Maintenance, Nickel plating, Pressurized water reactors, Reactor vessels, Stainless steel, Steel

Proceedings Papers

Constraint Effect on Fracture Mechanics Evaluation for an Under-Clad Crack in a Reactor Pressure Vessel Steel

Masaki Shimodaira, Tohru Tobita, Hisashi Takamizawa, Jinya Katsuyama, Satoshi Hanawa

Proc. ASME. PVP2020, Volume 1: Codes and Standards, V001T01A049, August 3, 2020

Paper No: PVP2020-21441

DOI: https://doi.org/10.1115/PVP2020-21441

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Topics: Finite element analysis, Fracture (Materials), Fracture mechanics, Fracture toughness, Reactor vessels, Steel, Surface cracks, Cladding systems (Building), Stress, Anisotropy

Proceedings Papers

Selection Criteria for Clad Materials to Use With a 316H Base Material for High Temperature Nuclear Reactor Cladded Components

B. Barua, M. C. Messner, R. I. Jetter, T.-L. Sham

Proc. ASME. PVP2020, Volume 1: Codes and Standards, V001T01A070, August 3, 2020

Paper No: PVP2020-21493

DOI: https://doi.org/10.1115/PVP2020-21493

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Topics: High temperature, Nuclear reactors, Creep, Design, Alloys, Temperature, Cladding systems (Building), Design methodology, Elastic moduli, Failure

Proceedings Papers

Properties of Cladding With Respect to RPV Integrity

Milan Brumovský

Proc. ASME. PVP2020, Volume 6: Materials and Fabrication, V006T06A076, August 3, 2020

Paper No: PVP2020-21445

DOI: https://doi.org/10.1115/PVP2020-21445

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Topics: Cladding systems (Building), Vessels

Proceedings Papers

Effect of Cladding-Induced Stresses on Crack Driving Force in the Fracture Analysis of Pressure Vessels

Julian Emslie, Josh White, Ben Pellereau, Andrew Wood

Proc. ASME. PVP2020, Volume 3: Design and Analysis, V003T03A056, August 3, 2020

Paper No: PVP2020-21583

DOI: https://doi.org/10.1115/PVP2020-21583

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Topics: Cladding systems (Building), Fracture (Materials), Fracture (Process), Pressure vessels, Stress

2 3 4 5

NARROW

Nickel Cladded Structural Components for Advanced Reactors

Further Developments in Nuclear Pressure Vessel Manufacture Using the Hot Isostatic Pressing Process and Thick-Section Electron Beam Welding

Post-Irradiation Fracture Toughness Characterization of Generation II FeCrAl Alloys

DetaClad™ Characterization for High-Temperature and High-Pressure Hydrogen Service

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

Mitigating LWR IronClad Fuel Cladding Dissolution Using Zinc Water Chemistry

Large-Scale Parametric Modeling of Spent Nuclear Fuel Dynamics in the 30 cm Package Drop Scenario

Finite Element Analysis of Ring Compression Testing for Used Nuclear Fuel Cladding

Effect of Plastic Constraint and Cladding on Semi-Elliptical Shaped Crack in Fracture Toughness Evaluation for a Reactor Pressure Vessel Steel

30 CM Horizontal Drop of a Surrogate 17x17 PWR Fuel Assembly

Thermal Analysis Evaluations Using the Dry Cask Simulator

Structural Dynamics Modeling of Spent Nuclear Fuel During Hypothetical Package Drop Events

Welding Tube to Tubesheet Joints for Corrosion Resisting Applications

A52M/SA502 Dissimilar Metal RPV Repair Weld: Evaluation of Different Techniques

A52M/SA52 Dissimilar Metal RPV Repair Weld: Experimental Evaluation and Post-Weld Characterizations

Application of Nickel Electroplating for PWR Reactor Pressure Vessel Cladding Repair

Constraint Effect on Fracture Mechanics Evaluation for an Under-Clad Crack in a Reactor Pressure Vessel Steel

Selection Criteria for Clad Materials to Use With a 316H Base Material for High Temperature Nuclear Reactor Cladded Components

Properties of Cladding With Respect to RPV Integrity

Effect of Cladding-Induced Stresses on Crack Driving Force in the Fracture Analysis of Pressure Vessels

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