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Proceedings Papers

Derivation of Input Distributions for Probabilistic Evaluation of PT/CT Contact in CANDU Reactors

Eric Nadeau, Adrian Baniak
Proc. ASME. PVP2024, Volume 2: Design & Analysis, V002T03A067, July 28–August 2, 2024
Publisher: American Society of Mechanical Engineers
Paper No: PVP2024-122832
https://doi.org/10.1115/PVP2024-122832
View Paper titled, Derivation of Input Distributions for Probabilistic Evaluation of PT/CT Contact in CANDU Reactors
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Topics: Arches, Candu reactors, Cold climates, Cracking (Materials), Creep, Design, Fittings, Fracture (Materials), Fracture (Process), Fuels
Proceedings Papers

Thermal-Structural and Shock Event Evaluations of the Fueling Pellet Injection System for ITER

Oscar Martinez, Sumalatha Yaski, Sarah Smith, Kara Godsey, David Rasmussen, Gary Lovett
Proc. ASME. PVP2024, Volume 2: Design & Analysis, V002T03A057, July 28–August 2, 2024
Publisher: American Society of Mechanical Engineers
Paper No: PVP2024-123447
https://doi.org/10.1115/PVP2024-123447
View Paper titled, Thermal-Structural and Shock Event Evaluations of the Fueling Pellet Injection System for ITER
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Topics: Shock (Mechanics), Design, Flight, Manufacturing, Plasmas (Ionized gases), Stress, Vacuum, Vessels, Carbon, Combustion
Proceedings Papers

On Structural Integrity Assessment of Conveyor Tube for Ice Plug Formation in the Fuel Receiving Bay

Reza Ghafouri-Azar
Proc. ASME. PVP2024, Volume 2: Design & Analysis, V002T03A037, July 28–August 2, 2024
Publisher: American Society of Mechanical Engineers
Paper No: PVP2024-129996
https://doi.org/10.1115/PVP2024-129996
View Paper titled, On Structural Integrity Assessment of Conveyor Tube for Ice Plug Formation in the Fuel Receiving Bay
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Topics: Conveyor systems, Finite element analysis, Fracture (Materials), Fracture (Process), Fuels, Ice
Proceedings Papers

Comparison of the Fatigue Life in Hydrogen Environment Using ASME Section VIII, Division 3 and ASME Section VIII, Division 2

Koray Kuscu, Mandeep Singh
Proc. ASME. PVP2023, Volume 1: Codes & Standards, V001T01A042, July 16–21, 2023
Publisher: American Society of Mechanical Engineers
Paper No: PVP2023-107120
https://doi.org/10.1115/PVP2023-107120
View Paper titled, Comparison of the Fatigue Life in Hydrogen Environment Using ASME Section VIII, Division 3 and ASME Section VIII, Division 2
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Topics: Fatigue life, Hydrogen, Hydrogen embrittlement, Fracture (Materials), Fatigue, American Petroleum Institute, Carbon, Emissions, Failure mechanisms, Fitness-for-service
Proceedings Papers

Fluid-Structure Interaction Simulations of a Rod Subjected to a Water Axial Flow in a Nuclear Core Relevant Configuration

Daniele Vivaldi, Roxan Pulicani
Proc. ASME. PVP2023, Volume 3: Fluid-Structure Interaction, V003T04A004, July 16–21, 2023
Publisher: American Society of Mechanical Engineers
Paper No: PVP2023-105808
https://doi.org/10.1115/PVP2023-105808
View Paper titled, Fluid-Structure Interaction Simulations of a Rod Subjected to a Water Axial Flow in a Nuclear Core Relevant Configuration
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Topics: Axial flow, Engineering simulation, Fluid structure interaction, Simulation, Water, Flow (Dynamics), Vibration, Computational fluid dynamics, Fluids, Turbulence
Proceedings Papers

Advancing the State-of-the-Art for Fretting Wear Testing

Salim El Bouzidi, Fabrice Guerout, Paul Feenstra, Anne McLellan, Brendan St. Pierre
Proc. ASME. PVP2023, Volume 3: Fluid-Structure Interaction, V003T04A006, July 16–21, 2023
Publisher: American Society of Mechanical Engineers
Paper No: PVP2023-105842
https://doi.org/10.1115/PVP2023-105842
View Paper titled, Advancing the State-of-the-Art for Fretting Wear Testing
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Topics: Vibration, Wear, Wear testing, High temperature, Testing, Excitation, Boilers, Chalk, Chemistry, Data acquisition
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
Publisher: American Society of Mechanical Engineers
Paper No: PVP2022-84517
https://doi.org/10.1115/PVP2022-84517
View Paper titled, Post-Irradiation Fracture Toughness Characterization of Generation II FeCrAl Alloys
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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
Publisher: American Society of Mechanical Engineers
Paper No: PVP2022-80557
https://doi.org/10.1115/PVP2022-80557
View Paper titled, Enhanced Mechanical Properties of Iron-Chromium-Aluminum Cladding for Light Water Reactor Fuels
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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
Publisher: American Society of Mechanical Engineers
Paper No: PVP2022-80559
https://doi.org/10.1115/PVP2022-80559
View Paper titled, Mitigating LWR IronClad Fuel Cladding Dissolution Using Zinc Water Chemistry
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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
Publisher: American Society of Mechanical Engineers
Paper No: PVP2022-84747
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
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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

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
Publisher: American Society of Mechanical Engineers
Paper No: PVP2022-84051
https://doi.org/10.1115/PVP2022-84051
View Paper titled, Hydrogen Permeability of Self-Healing Copolymers for Use in Hydrogen Delivery Applications
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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
Publisher: American Society of Mechanical Engineers
Paper No: PVP2022-83911
https://doi.org/10.1115/PVP2022-83911
View Paper titled, Finite Element Analysis of Ring Compression Testing for Used Nuclear Fuel Cladding
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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
Publisher: American Society of Mechanical Engineers
Paper No: PVP2022-84353
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
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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
Publisher: American Society of Mechanical Engineers
Paper No: PVP2022-84742
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
Publisher: American Society of Mechanical Engineers
Paper No: PVP2021-60533
https://doi.org/10.1115/PVP2021-60533
View Paper titled, 30 CM Horizontal Drop of a Surrogate 17x17 PWR Fuel Assembly
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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

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
Publisher: American Society of Mechanical Engineers
Paper No: PVP2021-62082
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
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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
Publisher: American Society of Mechanical Engineers
Paper No: PVP2021-61716
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
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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
Publisher: American Society of Mechanical Engineers
Paper No: PVP2021-61673
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
Publisher: American Society of Mechanical Engineers
Paper No: PVP2021-61617
https://doi.org/10.1115/PVP2021-61617
View Paper titled, Spent Nuclear Fuel Mechanical Loads in the General Package Drop Scenario
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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
Publisher: American Society of Mechanical Engineers
Paper No: PVP2021-61846
https://doi.org/10.1115/PVP2021-61846
View Paper titled, Thermal Analysis Evaluations Using the Dry Cask Simulator
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Topics: Thermal analysis, Fuels, Manufacturing, Computational fluid dynamics, Storage, Cladding systems (Building), Geometry, Heat, Stress, Temperature