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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
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

Effects of Strain Rate on Strain-Based Failure Assessment of Cask 1m-Puncture Drop for 304 Stainless Steel

Hune-Tae Kim, Jun-Min Seo, Ji-Hye Kim, Yun-Jae Kim
Proc. ASME. PVP2022, Volume 4B: Materials and Fabrication, V04BT06A050, July 17–22, 2022
Paper No: PVP2022-83765
https://doi.org/10.1115/PVP2022-83765
View Paper titled, Effects of Strain Rate on Strain-Based Failure Assessment of Cask 1m-Puncture Drop for 304 Stainless Steel
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Topics: Acceptance criteria, Failure, Fracture (Materials), Fracture (Process), Spent nuclear fuels, Stainless steel, Storage, Stress, Accidents, Boilers
Proceedings Papers

Thermal Modeling of Hanford Lead Canister’s Heater Bench Tests

Sarah R. Suffield, Christopher L. Grant, Nicholas A. Klymyshyn
Proc. ASME. PVP2022, Volume 5: Operations, Applications, and Components; Seismic Engineering; ASME Nondestructive Evaluation, Diagnosis and Prognosis (NDPD) Division, V005T07A023, July 17–22, 2022
Paper No: PVP2022-83737
https://doi.org/10.1115/PVP2022-83737
View Paper titled, Thermal Modeling of Hanford Lead Canister’s Heater Bench Tests
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Topics: Modeling, Testing, Storage, Computational fluid dynamics, Heat, Temperature, Uncertainty, Uncertainty analysis, Air flow, Computer simulation
Proceedings Papers

Computational Fluid Dynamics Modeling of Dry Cask Simulator With Crosswind

Ben J. Jensen, Sarah R. Suffield, Megan E. Higley
Proc. ASME. PVP2022, Volume 5: Operations, Applications, and Components; Seismic Engineering; ASME Nondestructive Evaluation, Diagnosis and Prognosis (NDPD) Division, V005T07A026, July 17–22, 2022
Paper No: PVP2022-84090
https://doi.org/10.1115/PVP2022-84090
View Paper titled, Computational Fluid Dynamics Modeling of Dry Cask Simulator With Crosswind
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Topics: Computational fluid dynamics, Modeling, Spent nuclear fuels, Stress corrosion cracking, Computer software, Sensitivity analysis, Spent fuel storage, Boiling water reactors, Containment vessels, Flow (Dynamics)
Proceedings Papers

Overview of Particle Deposition Models for Spent Nuclear Fuel Storage Systems

Sarah R. Suffield, Philip J. Jensen, William A. Perkins, Ben J. Jensen, Christopher L. Grant, Casey Spitz
Proc. ASME. PVP2022, Volume 5: Operations, Applications, and Components; Seismic Engineering; ASME Nondestructive Evaluation, Diagnosis and Prognosis (NDPD) Division, V005T07A025, July 17–22, 2022
Paper No: PVP2022-83982
https://doi.org/10.1115/PVP2022-83982
View Paper titled, Overview of Particle Deposition Models for Spent Nuclear Fuel Storage Systems
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Topics: Particulate matter, Spent fuel storage, Stress corrosion cracking, Storage, Computational fluid dynamics, Modeling, Spent nuclear fuels, Heat, Inspection, Nuclear power
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
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

Retracted: “Motion Model of Spent Fuel Rack Considering Two-Dimensional Gap Flow” [ASME 2020 Pressure Vessels & Piping Conference, Volume 4: Fluid-Structure Interaction, Virtual, Online, August 3, 2020, Conference Sponsors: Pressure Vessels and Piping Division, ISBN: 978-0-7918-8384-6, Copyright © 2020 by ASME. Paper No. PVP2020-21848, V004T04A004; 10 pages; doi: https://doi.org/10.1115/PVP2020-21848]

ASME
Proc. ASME. PVP2020, Volume 4: Fluid-Structure Interaction, V004T04A004, August 3, 2020
Paper No: PVP2020-21848
https://doi.org/10.1115/PVP2020-21848
View Paper titled, Retracted: “Motion Model of Spent Fuel Rack Considering Two-Dimensional Gap Flow” [ASME 2020 Pressure Vessels & Piping Conference, Volume 4: Fluid-Structure Interaction, Virtual, Online, August 3, 2020, Conference Sponsors: Pressure Vessels and Piping Division, ISBN: 978-0-7918-8384-6, Copyright © 2020 by ASME. Paper No. PVP2020-21848, V004T04A004; 10 pages; doi: https://doi.org/10.1115/PVP2020-21848]
Open the PDF for Retracted: “Motion Model of Spent Fuel Rack Considering Two-Dimensional Gap Flow” [ASME 2020 Pressure Vessels & Piping Conference, Volume 4: Fluid-Structure Interaction, Virtual, Online, August 3, 2020, Conference Sponsors: Pressure Vessels and Piping Division, ISBN: 978-0-7918-8384-6, Copyright © 2020 by ASME. Paper No. PVP2020-21848, V004T04A004; 10 pages; doi: https://doi.org/10.1115/PVP2020-21848] in another window
Topics: Flow (Dynamics), Fluid structure interaction, Pipes, Pressure vessels, Spent nuclear 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
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
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

Thermal Stress Analysis of a Spent Nuclear Fuel Canister

Ben J. Jensen, Charlton F. Campbell, Nicholas A. Klymyshyn
Proc. ASME. PVP2021, Volume 5: Operations, Applications, and Components; Seismic Engineering; Non-Destructive Examination, V005T07A024, July 13–15, 2021
Paper No: PVP2021-61608
https://doi.org/10.1115/PVP2021-61608
View Paper titled, Thermal Stress Analysis of a Spent Nuclear Fuel Canister
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Topics: Spent nuclear fuels, Thermal stresses, Stress, Temperature profiles, Computer simulation, Crack propagation, Earthquakes, Finite element analysis, Finite element model, Helium
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
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
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
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
https://doi.org/10.1115/PVP2021-61610
View Paper titled, Structural Dynamics Modeling of Spent Nuclear Fuel During Hypothetical Package Drop Events
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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

In-Service Inspection of Extended Dry Storage of Spent Nuclear Fuel, Part I: Crawler Technology Development

Ryan M. Meyer, Jeremy Renshaw, Jamie Beard, Jon Tatman, Matt Keene, Paul Plante, Neil Fales, Gabriel Grant, Uwe Wolf, Karan Mauskar, Darrell Dunn, Bruce Lin
Proc. ASME. PVP2021, Volume 5: Operations, Applications, and Components; Seismic Engineering; Non-Destructive Examination, V005T09A007, July 13–15, 2021
Paper No: PVP2021-62058
https://doi.org/10.1115/PVP2021-62058
View Paper titled, In-Service Inspection of Extended Dry Storage of Spent Nuclear Fuel, Part I: Crawler Technology Development
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Topics: In-service inspection, Robotics, Spent nuclear fuels, Storage, Technology development
Proceedings Papers

Inservice Inspection of Extended Dry Storage of Spent Nuclear Fuel, Part II: NDE/Sensor Technology Development and Codification

Ryan M. Meyer, Jeremy Renshaw, Kenn Hunter, Mike Orihuela, Jim Stadler, Karan Mauskar, Uwe Wolf, Marvin Klein, Max Weidmann, Bradley Bobbs, Darrell Dunn, Bruce Lin
Proc. ASME. PVP2021, Volume 5: Operations, Applications, and Components; Seismic Engineering; Non-Destructive Examination, V005T09A008, July 13–15, 2021
Paper No: PVP2021-62069
https://doi.org/10.1115/PVP2021-62069
View Paper titled, Inservice Inspection of Extended Dry Storage of Spent Nuclear Fuel, Part II: NDE/Sensor Technology Development and Codification
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Topics: In-service inspection, Nondestructive evaluation, Sensors, Spent nuclear fuels, Storage, Technology development
Proceedings Papers

Technical Basis Summary for Code Case N-860: Inspection Requirements and Evaluation Standards for Spent Nuclear Fuel Storage and Transportation Containment Systems

John E. Broussard, III
Proc. ASME. PVP2021, Volume 1: Codes and Standards, V001T01A061, July 13–15, 2021
Paper No: PVP2021-64176
https://doi.org/10.1115/PVP2021-64176
View Paper titled, Technical Basis Summary for Code Case N-860: Inspection Requirements and Evaluation Standards for Spent Nuclear Fuel Storage and Transportation Containment Systems
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Topics: Containment systems, Inspection, Spent fuel storage, Spent nuclear fuels, Stress corrosion cracking, Transportation systems, In-service inspection, Acceptance criteria, ASME Boiler and Pressure Vessel Code, Fracture (Materials)
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
https://doi.org/10.1115/PVP2021-62412
View Paper titled, Investigation of the Irradiation Effect on the Dynamics of Nuclear Fuel Bundles
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Topics: Dynamics (Mechanics), Fuel rods, Irradiation (Radiation exposure), Fuels, Flow (Dynamics), Constitutive equations, Coolants, Dynamic response, Mechanical properties, Pressure
Proceedings Papers

Investigation of Chloride-Induced Stress Corrosion Cracking for AISI 304/304L Stainless Steel Using Notched Bar Specimens

Jae-Yoon Jeong, Yun-Jae Kim, Poh-Sang Lam, Andrew Duncan, Myeong-Woo Lee
Proc. ASME. PVP2020, Volume 6: Materials and Fabrication, V006T06A106, August 3, 2020
Paper No: PVP2020-21399
https://doi.org/10.1115/PVP2020-21399
View Paper titled, Investigation of Chloride-Induced Stress Corrosion Cracking for AISI 304/304L Stainless Steel Using Notched Bar Specimens
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Topics: Corrosion, Spent nuclear fuels, Stainless steel, Stress corrosion cracking
Proceedings Papers

Comparative Stress Analyses of Dropped Spent Nuclear Fuel Assembly in a Prototypal Cask

Sae-Han-Sol Kang, Dong-Hyun Kim, Yoon-Suk Chang, Sang-Hwan Lee
Proc. ASME. PVP2020, Volume 6: Materials and Fabrication, V006T06A107, August 3, 2020
Paper No: PVP2020-21510
https://doi.org/10.1115/PVP2020-21510
View Paper titled, Comparative Stress Analyses of Dropped Spent Nuclear Fuel Assembly in a Prototypal Cask
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Topics: Finite element analysis, Manufacturing, Spent nuclear fuels, Stress analysis (Engineering)
Proceedings Papers

CISCC Experiment of a Large Plate Sectioned From a Spent Nuclear Fuel Canister

Andrew J. Duncan, Poh-Sang Lam, Robert L. Sindelar
Proc. ASME. PVP2020, Volume 6: Materials and Fabrication, V006T06A108, August 3, 2020
Paper No: PVP2020-21774
https://doi.org/10.1115/PVP2020-21774
View Paper titled, CISCC Experiment of a Large Plate Sectioned From a Spent Nuclear Fuel Canister
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Topics: Deliquescence, Fracture (Materials), Spent nuclear fuels, Stress, Stress corrosion cracking, Welding, Electrical discharge machining, Corrosion, Stainless steel, Temperature