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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

Deployment of Laser Peening to Prevent CISCC of Nuclear Fuel Dry Storage Canisters

Lloyd Hackel, Jon Rankin, Matt Walter, C. Brent Dane, William Neuman, Pierre Oneid, Gareth Thomas, Fred Bidrawn
Proc. ASME. PVP2020, Volume 8: Operations, Applications, and Components, V008T08A033, August 3, 2020
Publisher: American Society of Mechanical Engineers
Paper No: PVP2020-21045
https://doi.org/10.1115/PVP2020-21045
View Paper titled, Deployment of Laser Peening to Prevent CISCC of Nuclear Fuel Dry Storage Canisters
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Topics: Alloys, Laser hardening, Nuclear fuels, Spent nuclear fuels, Stainless steel, Storage, Stress corrosion cracking
Proceedings Papers

Temperature Prediction of a Used Nuclear Fuel Cask With Different Gas Backfills

Megan Higley, Mustafa Hadj-Nacer, Miles Greiner
Proc. ASME. PVP2020, Volume 8: Operations, Applications, and Components, V008T08A036, August 3, 2020
Publisher: American Society of Mechanical Engineers
Paper No: PVP2020-21116
https://doi.org/10.1115/PVP2020-21116
View Paper titled, Temperature Prediction of a Used Nuclear Fuel Cask With Different Gas Backfills
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Topics: Computational fluid dynamics, Nuclear fuels, Temperature, Cladding systems (Building), Gases, Heat, Helium, Drying, Electricity (Physics), Engineering simulation
Proceedings Papers

Overview of UK Policy and Research Landscape Relevant to Deploying Advanced Nuclear Technologies in the UK

Nicholas Underwood, Paul Nevitt, Andrew Howarth, Nicholas Barron
Proc. ASME. PVP2020, Volume 1: Codes and Standards, V001T01A043, August 3, 2020
Publisher: American Society of Mechanical Engineers
Paper No: PVP2020-21790
https://doi.org/10.1115/PVP2020-21790
View Paper titled, Overview of UK Policy and Research Landscape Relevant to Deploying Advanced Nuclear Technologies in the UK
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Topics: Advanced materials, Boiling, Carbon, Climate change, Construction, Cooling, Cooling systems, Cutting, Cycles, Design
Proceedings Papers

Finite Element Verification of Engineering Equations for Prediction of Structural Strength of Annulus Spacers in CANDU Nuclear Reactors

Preeti Doddihal, Dennis Kawa, Douglas Scarth, Yu Chen
Proc. ASME. PVP2019, Volume 6A: Materials and Fabrication, V06AT06A013, July 14–19, 2019
Publisher: American Society of Mechanical Engineers
Paper No: PVP2019-93671
https://doi.org/10.1115/PVP2019-93671
View Paper titled, Finite Element Verification of Engineering Equations for Prediction of Structural Strength of Annulus Spacers in CANDU Nuclear Reactors
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Topics: Annulus, Finite element analysis, Nuclear reactors, Fracture (Materials), Fracture (Process), Strips, Fuels, Irradiation (Radiation exposure), Pressure, Stress
Proceedings Papers

Modeling Shock and Vibration on Used Nuclear Fuel During Normal Conditions of Transportation

Nicholas Klymyshyn, Pavlo Ivanusa, Kevin Kadooka, Casey Spitz
Proc. ASME. PVP2019, Volume 7: Operations, Applications, and Components, V007T07A027, July 14–19, 2019
Publisher: American Society of Mechanical Engineers
Paper No: PVP2019-93619
https://doi.org/10.1115/PVP2019-93619
View Paper titled, Modeling Shock and Vibration on Used Nuclear Fuel During Normal Conditions of Transportation
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Topics: Dynamics (Mechanics), Modeling, Nuclear fuels, Shock (Mechanics), Transportation systems, Vibration
Proceedings Papers

Progress Report on Stress Intensity Factor and J-Integral Estimation for Nuclear Fuel Canisters Under Mechanical Loading

Ji-Su Kim, Jae-Min Gim, Yun-Jae Kim, Poh-Sang Lam
Proc. ASME. PVP2018, Volume 6B: Materials and Fabrication, V06BT06A070, July 15–20, 2018
Publisher: American Society of Mechanical Engineers
Paper No: PVP2018-84966
https://doi.org/10.1115/PVP2018-84966
View Paper titled, Progress Report on Stress Intensity Factor and J-Integral Estimation for Nuclear Fuel Canisters Under Mechanical Loading
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Topics: Nuclear fuels, Stress, Fracture (Materials), American Petroleum Institute, Finite element analysis, Fracture mechanics, Spent nuclear fuels, Surface cracks, Welding
Proceedings Papers

Comparison of DSMC and CFD Models of Heat Transfer in a Rarefied Two-Dimensional Geometry

Dilesh Maharjan, Mustafa Hadj-Nacer, Miles Greiner, Stefan K. Stefanov
Proc. ASME. PVP2018, Volume 7: Operations, Applications, and Components, V007T07A031, July 15–20, 2018
Publisher: American Society of Mechanical Engineers
Paper No: PVP2018-84986
https://doi.org/10.1115/PVP2018-84986
View Paper titled, Comparison of DSMC and CFD Models of Heat Transfer in a Rarefied Two-Dimensional Geometry
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Topics: Computational fluid dynamics, Geometry, Heat transfer, Temperature, Cladding systems (Building), Helium, Simulation, Drying, Pressure, Vacuum
Proceedings Papers

Temperature Prediction of a TN-32 Used Nuclear Fuel Canister Subjected to Vacuum Drying Conditions

Megan Higley, Mustafa Hadj-Nacer, Miles Greiner
Proc. ASME. PVP2018, Volume 7: Operations, Applications, and Components, V007T07A041, July 15–20, 2018
Publisher: American Society of Mechanical Engineers
Paper No: PVP2018-84844
https://doi.org/10.1115/PVP2018-84844
View Paper titled, Temperature Prediction of a TN-32 Used Nuclear Fuel Canister Subjected to Vacuum Drying Conditions
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Topics: Drying, Nuclear fuels, Temperature, Vacuum, Cladding systems (Building), Heat, Computational fluid dynamics, Engineering simulation, Helium, Pressurized water reactors
Proceedings Papers

Temperature Jump Measurement at Stainless Steel and Helium Interface: Application to Used Nuclear Fuel Vacuum Drying Process

Cody Zampella, Mustafa Hadj-Nacer, Miles Greiner
Proc. ASME. PVP2018, Volume 7: Operations, Applications, and Components, V007T07A042, July 15–20, 2018
Publisher: American Society of Mechanical Engineers
Paper No: PVP2018-84848
https://doi.org/10.1115/PVP2018-84848
View Paper titled, Temperature Jump Measurement at Stainless Steel and Helium Interface: Application to Used Nuclear Fuel Vacuum Drying Process
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Topics: Drying, Helium, Nuclear fuels, Stainless steel, Temperature, Vacuum, Cylinders, Fuels, Engineering simulation, Heat flux
Proceedings Papers

Temperature Measurement of an Array of Heated Rods Subjected to Vacuum Drying Conditions

Dilesh Maharjan, Mustafa Hadj-Nacer, Miles Greiner
Proc. ASME. PVP2017, Volume 3A: Design and Analysis, V03AT03A019, July 16–20, 2017
Publisher: American Society of Mechanical Engineers
Paper No: PVP2017-66001
https://doi.org/10.1115/PVP2017-66001
View Paper titled, Temperature Measurement of an Array of Heated Rods Subjected to Vacuum Drying Conditions
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Topics: Drying, Rods, Temperature measurement, Vacuum, Temperature, Fuels, Plates (structures), Pressure, Helium, Boiling water reactors
Proceedings Papers

Experimentally Benchmarked Computational Fluid Dynamics Simulations of a 7×7 Array of Heated Rods Within a Square-Cross-Section Enclosure Filled With Rarefied Helium

Dilesh Maharjan, Mustafa Hadj-Nacer, Miles Greiner
Proc. ASME. PVP2017, Volume 3A: Design and Analysis, V03AT03A020, July 16–20, 2017
Publisher: American Society of Mechanical Engineers
Paper No: PVP2017-66002
https://doi.org/10.1115/PVP2017-66002
View Paper titled, Experimentally Benchmarked Computational Fluid Dynamics Simulations of a 7×7 Array of Heated Rods Within a Square-Cross-Section Enclosure Filled With Rarefied Helium
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Topics: Computational fluid dynamics, Engineering simulation, Helium, Rods, Simulation, Temperature, Heat, Drying, Manufacturing, Nuclear fuels
Proceedings Papers

A Numerical Study on Fracture Toughness of CANDU Pressure Tube

Elisabeth Keim, Tomas Nicak, Bogdan Wasiluk
Proc. ASME. PVP2017, Volume 6A: Materials and Fabrication, V06AT06A076, July 16–20, 2017
Publisher: American Society of Mechanical Engineers
Paper No: PVP2017-65757
https://doi.org/10.1115/PVP2017-65757
View Paper titled, A Numerical Study on Fracture Toughness of CANDU Pressure Tube
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Topics: Fracture toughness, Pressure, Fracture (Materials), Hydrogen, Stress, Zirconium, Alloys, Brittleness, Deformation, Displacement
Proceedings Papers

Improved Engineering Process-Zone Model for Evaluation of Structural Strength of Annulus Spacers in CANDU Nuclear Reactors

Cheng Liu, Leonid Gutkin, Douglas Scarth
Proc. ASME. PVP2017, Volume 6A: Materials and Fabrication, V06AT06A040, July 16–20, 2017
Publisher: American Society of Mechanical Engineers
Paper No: PVP2017-66193
https://doi.org/10.1115/PVP2017-66193
View Paper titled, Improved Engineering Process-Zone Model for Evaluation of Structural Strength of Annulus Spacers in CANDU Nuclear Reactors
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Topics: Annulus, Nuclear reactors, Pressure, Stress, Design, Fuels, Separation (Technology), Traction, Damage, Displacement
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
Publisher: American Society of Mechanical Engineers
Paper No: PVP2016-63164
https://doi.org/10.1115/PVP2016-63164
View Paper titled, Hydrogen Diffusion in FeCrAl Alloys for Light Water Reactors Cladding Applications
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Topics: Alloys, Cladding systems (Building), Diffusion (Physics), Hydrogen, Light water reactors, Coolants, Fuels, Zirconium alloys, Accidents, Aluminum
Proceedings Papers

Experimentally-Benchmarked Computational Fluid Dynamics Simulations of an Array of Heated Rods Within a Square-Cross-Section Helium-Filled Pressure Vessel

Dilesh Maharjan, Mustafa Hadj-Nacer, Narayana R. Chalasani, Miles Greiner
Proc. ASME. PVP2016, Volume 7: Operations, Applications and Components, V007T07A036, July 17–21, 2016
Publisher: American Society of Mechanical Engineers
Paper No: PVP2016-64005
https://doi.org/10.1115/PVP2016-64005
View Paper titled, Experimentally-Benchmarked Computational Fluid Dynamics Simulations of an Array of Heated Rods Within a Square-Cross-Section Helium-Filled Pressure Vessel
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Topics: Computational fluid dynamics, Engineering simulation, Helium, Pressure vessels, Rods, Simulation, Heat, Manufacturing, Plates (structures), Temperature
Proceedings Papers

Laying the Groundwork for a Large-Scale Spent Nuclear Fuel Transportation System

Matthew Feldman, Kevin Connolly
Proc. ASME. PVP2015, Volume 7: Operations, Applications and Components, V007T07A050, July 19–23, 2015
Publisher: American Society of Mechanical Engineers
Paper No: PVP2015-45921
https://doi.org/10.1115/PVP2015-45921
View Paper titled, Laying the Groundwork for a Large-Scale Spent Nuclear Fuel Transportation System
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Topics: Spent nuclear fuels, Transportation systems, Storage, Hardware, Modeling, Nuclear fuels, Nuclear power, Radioactive wastes, Railroads, Rails
Proceedings Papers

Closure Bolt Modeling for Seal Evaluation Under Extreme Thermal Loads

Nicholas A. Klymyshyn, Harold E. Adkins, Jason M. Piotter
Proc. ASME. PVP2015, Volume 7: Operations, Applications and Components, V007T07A052, July 19–23, 2015
Publisher: American Society of Mechanical Engineers
Paper No: PVP2015-45941
https://doi.org/10.1115/PVP2015-45941
View Paper titled, Closure Bolt Modeling for Seal Evaluation Under Extreme Thermal Loads
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Topics: Modeling, Stress, Accidents, Fire, Nuclear fuels, Thermal expansion, Thread, Transport packages, Collapse, Dynamics (Mechanics)
Proceedings Papers

Monitoring Helium Integrity in Welded Canisters

Y. Y. Liu, H.-C. Tsai, M. Nutt
Proc. ASME. PVP2015, Volume 7: Operations, Applications and Components, V007T07A053, July 19–23, 2015
Publisher: American Society of Mechanical Engineers
Paper No: PVP2015-45947
https://doi.org/10.1115/PVP2015-45947
View Paper titled, Monitoring Helium Integrity in Welded Canisters
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Topics: Cladding systems (Building), Engineering prototypes, Explosives, Fuel rods, Fuels, Heat, Helium, Hydrogen, Nuclear fuels, Oxidation
Proceedings Papers

Application of the ASME Code to Radioactive Material Packaging/Cask: Lessons Learned From the 2014 DOE Training Course

Zenghu Han, Ralph Fabian, Ron Pope, Yung Liu, James Shuler
Proc. ASME. PVP2015, Volume 7: Operations, Applications and Components, V007T07A054, July 19–23, 2015
Publisher: American Society of Mechanical Engineers
Paper No: PVP2015-45955
https://doi.org/10.1115/PVP2015-45955
View Paper titled, Application of the ASME Code to Radioactive Material Packaging/Cask: Lessons Learned From the 2014 DOE Training Course
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Topics: ASME Standards, Packaging, Radioactive substances, Storage, Transportation systems, Design, Testing, Containment, Fuels, Manufacturing