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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
View Paper titled, Post-Irradiation Fracture Toughness Characterization of Generation II FeCrAl Alloys
Click here to open pdf in another window PDF for Post-Irradiation Fracture Toughness Characterization of Generation II FeCrAl Alloys
Topics: Accidents, Alloys, Cladding systems (Building), Embrittlement, Fracture toughness, Fuels, Hardening, Irradiation (Radiation exposure)
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
View Paper titled, Enhanced Mechanical Properties of Iron-Chromium-Aluminum Cladding for Light Water Reactor Fuels
Click here to open pdf in another window PDF for Enhanced Mechanical Properties of Iron-Chromium-Aluminum Cladding for Light Water Reactor Fuels
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
View Paper titled, Mitigating LWR IronClad Fuel Cladding Dissolution Using Zinc Water Chemistry
Click here to open pdf in another window PDF for Mitigating LWR IronClad Fuel Cladding Dissolution Using Zinc Water Chemistry
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
View Paper titled, Large-Scale Parametric Modeling of Spent Nuclear Fuel Dynamics in the 30 cm Package Drop Scenario
Click here to open pdf in another window PDF for Large-Scale Parametric Modeling of Spent Nuclear Fuel Dynamics in the 30 cm Package Drop Scenario
Topics: Dynamics (Mechanics), Modeling, Spent nuclear fuels, Fuels, Manufacturing, Simulation, Stress, Boiling water reactors, Cladding systems (Building), Fuel rods
Proceedings Papers

Hydrogen Permeability of Self-Healing Copolymers for Use in Hydrogen Delivery Applications

Dale Hitchcock, Timothy Krentz, Anastasia Mullins, Charles James, Qianhui Liu, Siyang Wang, Samruddhi Gaikwad, Marek W. Urban
Proc. ASME. PVP2022, Volume 4B: Materials and Fabrication, V04BT06A027, July 17–22, 2022
Paper No: PVP2022-84051
DOI: https://doi.org/10.1115/PVP2022-84051
View Paper titled, Hydrogen Permeability of Self-Healing Copolymers for Use in Hydrogen Delivery Applications
Click here to open pdf in another window PDF for Hydrogen Permeability of Self-Healing Copolymers for Use in Hydrogen Delivery Applications
Topics: Copolymers, Hydrogen, Permeability, Molecular weight, Service life (Equipment), Elastomers, Fuels, Membranes, Polymers, Pressure
Proceedings Papers

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

Zenghu Han, Michael C. Billone, Yung Y. Liu
Proc. ASME. PVP2022, Volume 5: Operations, Applications, and Components; Seismic Engineering; ASME Nondestructive Evaluation, Diagnosis and Prognosis (NDPD) Division, V005T07A024, July 17–22, 2022
Paper No: PVP2022-83911
DOI: https://doi.org/10.1115/PVP2022-83911
View Paper titled, Finite Element Analysis of Ring Compression Testing for Used Nuclear Fuel Cladding
Click here to open pdf in another window PDF for Finite Element Analysis of Ring Compression Testing for Used Nuclear Fuel Cladding
Topics: Cladding systems (Building), Compression, Finite element analysis, Nuclear fuels, Testing, Storage, Transportation systems, Ductility, Fuels, Mechanical properties
Proceedings Papers

An Estimate of Spent Nuclear Fuel Mechanical Loads in the General 30 cm Package Drop Scenario

Nicholas Klymyshyn, Kevin Kadooka, Casey Spitz, James Fitzpatrick
Proc. ASME. PVP2022, Volume 5: Operations, Applications, and Components; Seismic Engineering; ASME Nondestructive Evaluation, Diagnosis and Prognosis (NDPD) Division, V005T07A028, July 17–22, 2022
Paper No: PVP2022-84353
DOI: https://doi.org/10.1115/PVP2022-84353
View Paper titled, An Estimate of Spent Nuclear Fuel Mechanical Loads in the General 30 cm Package Drop Scenario
Click here to open pdf in another window PDF for An Estimate of Spent Nuclear Fuel Mechanical Loads in the General 30 cm Package Drop Scenario
Topics: Spent nuclear fuels, Stress, Fuels, Manufacturing, Damage, Modeling, Boiling water reactors, Boundary element methods, Collaboration, Design
Proceedings Papers

Probabilistic Control Rod Failure Analysis for a Nominal Molten Salt Reactor

Henry Cathcart, James Finley, John Taylor, Alexander Frost
Proc. ASME. PVP2022, Volume 1: Codes and Standards, V001T01A055, July 17–22, 2022
Paper No: PVP2022-84742
DOI: https://doi.org/10.1115/PVP2022-84742
View Paper titled, Probabilistic Control Rod Failure Analysis for a Nominal Molten Salt Reactor
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Topics: Atoms, Bricks, Carbon, Dimensions, Emissions, Failure, Failure analysis, Finite element analysis, Fluence (Radiation measurement), Fuels
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
View Paper titled, 30 CM Horizontal Drop of a Surrogate 17x17 PWR Fuel Assembly
Click here to open pdf in another window PDF for 30 CM Horizontal Drop of a Surrogate 17x17 PWR Fuel Assembly
Topics: Cladding systems (Building), Fuels, Manufacturing, Pressure, Pressurized water reactors, Spent nuclear fuels, Stress-strain curves, Arches, Bending (Stress), Blanks
Proceedings Papers

Transient Thermal Modeling of the High Burnup Demonstration Research Project Cask Using STAR-CCM+ and COBRA-SFS

D. J. Richmond, J. A. Fort, S. R. Suffield
Proc. ASME. PVP2021, Volume 5: Operations, Applications, and Components; Seismic Engineering; Non-Destructive Examination, V005T07A031, July 13–15, 2021
Paper No: PVP2021-62082
DOI: https://doi.org/10.1115/PVP2021-62082
View Paper titled, Transient Thermal Modeling of the High Burnup Demonstration Research Project Cask Using STAR-CCM+ and COBRA-SFS
Click here to open pdf in another window PDF for Transient Thermal Modeling of the High Burnup Demonstration Research Project Cask Using STAR-CCM+ and COBRA-SFS
Topics: Computational fluid dynamics, Design, Modeling, Temperature, Transients (Dynamics), Drying, Steady state, Fuels, Spent nuclear fuels, Storage
Proceedings Papers

Modeling and Sensitivity Analysis of the TN-32 UNF Cask: Comparison With the HBU Project Data

Megan Higley, Mustafa Hadj-Nacer, Miles Greiner
Proc. ASME. PVP2021, Volume 5: Operations, Applications, and Components; Seismic Engineering; Non-Destructive Examination, V005T07A027, July 13–15, 2021
Paper No: PVP2021-61716
DOI: https://doi.org/10.1115/PVP2021-61716
View Paper titled, Modeling and Sensitivity Analysis of the TN-32 UNF Cask: Comparison With the HBU Project Data
Click here to open pdf in another window PDF for Modeling and Sensitivity Analysis of the TN-32 UNF Cask: Comparison With the HBU Project Data
Topics: Collaboration, Modeling, Sensitivity analysis, Storage, Temperature, Engineering simulation, Natural convection, Rails, Simulation, Boundary-value problems
Proceedings Papers

Research on Modal Parameter Identification of Fuel Assembly Based on POD Method

Xuan Huang, Fengchun Cai, Shuai Liu, Zhipeng Feng, Jian Liu, Xiaozhou Jiang, Ke Zhang
Proc. ASME. PVP2021, Volume 5: Operations, Applications, and Components; Seismic Engineering; Non-Destructive Examination, V005T08A008, July 13–15, 2021
Paper No: PVP2021-61673
DOI: https://doi.org/10.1115/PVP2021-61673
View Paper titled, Research on Modal Parameter Identification of Fuel Assembly Based on POD Method
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Topics: Fuels, Manufacturing, Transfer functions, Damping, Dynamic analysis, Excitation, Finite element model, Principal component analysis, Signals, Transients (Dynamics)
Proceedings Papers

Spent Nuclear Fuel Mechanical Loads in the General Package Drop Scenario

Nicholas Klymyshyn, Casey Spitz, Pavlo Ivanusa, Kevin Kadooka, James Fitzpatrick
Proc. ASME. PVP2021, Volume 5: Operations, Applications, and Components; Seismic Engineering; Non-Destructive Examination, V005T07A026, July 13–15, 2021
Paper No: PVP2021-61617
DOI: https://doi.org/10.1115/PVP2021-61617
View Paper titled, Spent Nuclear Fuel Mechanical Loads in the General Package Drop Scenario
Click here to open pdf in another window PDF for Spent Nuclear Fuel Mechanical Loads in the General Package Drop Scenario
Topics: Spent nuclear fuels, Stress, Damage, Manufacturing, Boundary element methods, Design, Dynamic analysis, Finite element analysis, Finite element model, Fuels
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
View Paper titled, Thermal Analysis Evaluations Using the Dry Cask Simulator
Click here to open pdf in another window PDF for Thermal Analysis Evaluations Using the Dry Cask Simulator
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
View Paper titled, Structural Dynamics Modeling of Spent Nuclear Fuel During Hypothetical Package Drop Events
Click here to open pdf in another window PDF for Structural Dynamics Modeling of Spent Nuclear Fuel During Hypothetical Package Drop Events
Topics: Modeling, Spent nuclear fuels, Structural dynamics, Fuels, Shock (Mechanics), Transportation systems, Boundary element methods, Buckling, Cladding systems (Building), Design
Proceedings Papers

Analysis of Test Method to Extract Material Properties From Candu Fuel Channel Spacers Made of Helical Springs

Donald Metzger, Andre Gagnon, Tejasvi Kashyap
Proc. ASME. PVP2021, Volume 2: Computer Technology and Bolted Joints; Design and Analysis, V002T02A010, July 13–15, 2021
Paper No: PVP2021-62917
DOI: https://doi.org/10.1115/PVP2021-62917
View Paper titled, Analysis of Test Method to Extract Material Properties From Candu Fuel Channel Spacers Made of Helical Springs
Click here to open pdf in another window PDF for Analysis of Test Method to Extract Material Properties From Candu Fuel Channel Spacers Made of Helical Springs
Topics: Fuels, Materials properties, Springs, Finite element analysis, Stress, Testing, Approximation, Boundary-value problems, Friction, Materials degradation
Proceedings Papers

Fracture Analysis of Reactor Pressure Vessel Lower Head Considering Core Meltdown Accident

Yaroslav Dubyk, Vitalii Antonchenko, Maksym Zarazovskii
Proc. ASME. PVP2021, Volume 2: Computer Technology and Bolted Joints; Design and Analysis, V002T03A063, July 13–15, 2021
Paper No: PVP2021-62062
DOI: https://doi.org/10.1115/PVP2021-62062
View Paper titled, Fracture Analysis of Reactor Pressure Vessel Lower Head Considering Core Meltdown Accident
Click here to open pdf in another window PDF for Fracture Analysis of Reactor Pressure Vessel Lower Head Considering Core Meltdown Accident
Topics: Accidents, Fracture (Materials), Reactor vessels, Vessels, Boundary-value problems, Cavities, Cooling, Creep, Floods, Fracture mechanics
Proceedings Papers

Torsional Fatigue Test Applicable to Helical Spring Material Used in Candu Fuel Channel Spacers

Andre Gagnon, Tejasvi Kashyap, Don Metzger
Proc. ASME. PVP2021, Volume 2: Computer Technology and Bolted Joints; Design and Analysis, V002T02A011, July 13–15, 2021
Paper No: PVP2021-63016
DOI: https://doi.org/10.1115/PVP2021-63016
View Paper titled, Torsional Fatigue Test Applicable to Helical Spring Material Used in Candu Fuel Channel Spacers
Click here to open pdf in another window PDF for Torsional Fatigue Test Applicable to Helical Spring Material Used in Candu Fuel Channel Spacers
Topics: Fatigue testing, Fuels, Springs, Stress, Structural elements (Construction), Cycles, Dimensions, Fatigue, Fatigue analysis, Materials degradation
Proceedings Papers

Investigation of the Irradiation Effect on the Dynamics of Nuclear Fuel Bundles

Osama Elbanhawy, Marwan Hassan, Atef Mohany, Hossam Kishawy
Proc. ASME. PVP2021, Volume 3: Fluid Structure Interaction; High Pressure Technology, V003T04A007, July 13–15, 2021
Paper No: PVP2021-62412
DOI: https://doi.org/10.1115/PVP2021-62412
View Paper titled, Investigation of the Irradiation Effect on the Dynamics of Nuclear Fuel Bundles
Click here to open pdf in another window PDF for Investigation of the Irradiation Effect on the Dynamics of Nuclear Fuel Bundles
Topics: Dynamics (Mechanics), Fuel rods, Irradiation (Radiation exposure), Fuels, Flow (Dynamics), Constitutive equations, Coolants, Dynamic response, Mechanical properties, Pressure
Proceedings Papers

Fabrication and Assembly of the First Accident Tolerant Fuel Concept for TREAT Testing

Connor Woolum, D. Devin Imholte, Austin Fleming, David Kamerman, Korbin Tritthart
Proc. ASME. PVP2020, Volume 6: Materials and Fabrication, V006T06A078, August 3, 2020
Paper No: PVP2020-21620
DOI: https://doi.org/10.1115/PVP2020-21620
View Paper titled, Fabrication and Assembly of the First Accident Tolerant Fuel Concept for TREAT Testing
Click here to open pdf in another window PDF for Fabrication and Assembly of the First Accident Tolerant Fuel Concept for TREAT Testing
Topics: Accidents, Fuels, Irradiation (Radiation exposure), Manufacturing, Testing, Cladding systems (Building), Pressurized water reactors, Transients (Dynamics), Design, Fuel systems