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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

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

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

Paper No: PVP2020-21045

DOI: https://doi.org/10.1115/PVP2020-21045

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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

Paper No: PVP2020-21116

DOI: https://doi.org/10.1115/PVP2020-21116

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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

Paper No: PVP2020-21790

DOI: https://doi.org/10.1115/PVP2020-21790

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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

Paper No: PVP2019-93671

DOI: https://doi.org/10.1115/PVP2019-93671

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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

Paper No: PVP2019-93619

DOI: https://doi.org/10.1115/PVP2019-93619

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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

Paper No: PVP2018-84966

DOI: https://doi.org/10.1115/PVP2018-84966

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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

Paper No: PVP2018-84986

DOI: https://doi.org/10.1115/PVP2018-84986

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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

Paper No: PVP2018-84844

DOI: https://doi.org/10.1115/PVP2018-84844

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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

Paper No: PVP2018-84848

DOI: https://doi.org/10.1115/PVP2018-84848

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Topics: Drying, Helium, Nuclear fuels, Stainless steel, Temperature, Vacuum, Cylinders, Fuels, Engineering simulation, Heat flux

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

Paper No: PVP2017-66002

DOI: https://doi.org/10.1115/PVP2017-66002

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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

Paper No: PVP2017-65757

DOI: https://doi.org/10.1115/PVP2017-65757

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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

Paper No: PVP2017-66193

DOI: https://doi.org/10.1115/PVP2017-66193

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Topics: Annulus, Nuclear reactors, Pressure, Stress, Design, Fuels, Separation (Technology), Traction, Damage, Displacement

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

Paper No: PVP2017-66001

DOI: https://doi.org/10.1115/PVP2017-66001

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Topics: Drying, Rods, Temperature measurement, Vacuum, Temperature, Fuels, Plates (structures), Pressure, Helium, Boiling water reactors

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

Paper No: PVP2016-63164

DOI: https://doi.org/10.1115/PVP2016-63164

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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

Paper No: PVP2016-64005

DOI: https://doi.org/10.1115/PVP2016-64005

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Topics: Computational fluid dynamics, Engineering simulation, Helium, Pressure vessels, Rods, Simulation, Heat, Manufacturing, Plates (structures), Temperature

Proceedings Papers

Geometrically-Accurate-Three-Dimensional Simulations of a Used Nuclear Fuel Canister Filled With Helium

Triton Manzo, Mustafa-Hadj Nacer, Miles Greiner

Proc. ASME. PVP2015, Volume 7: Operations, Applications and Components, V007T07A046, July 19–23, 2015

Paper No: PVP2015-45851

DOI: https://doi.org/10.1115/PVP2015-45851

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Topics: Engineering simulation, Helium, Nuclear fuels, Simulation, Temperature, Cladding systems (Building), Fuels, Heat, Natural convection, Heat transfer

Proceedings Papers

Failure Criteria for Unirradiated PWR Cladding Subjected to Ring Compression Tests

Jesus Ruiz-Hervias, Miguel Angel Martin-Rengel, Francisco Javier Gomez-Sanchez

Proc. ASME. PVP2015, Volume 7: Operations, Applications and Components, V007T07A043, July 19–23, 2015

Paper No: PVP2015-45793

DOI: https://doi.org/10.1115/PVP2015-45793

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Topics: Cladding systems (Building), Compression, Failure, Pressurized water reactors, Drying, Spent nuclear fuels, Storage, Accidents, Computer simulation, Manufacturing

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

Paper No: PVP2015-45921

DOI: https://doi.org/10.1115/PVP2015-45921

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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

Paper No: PVP2015-45941

DOI: https://doi.org/10.1115/PVP2015-45941

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Topics: Modeling, Stress, Accidents, Fire, Nuclear fuels, Thermal expansion, Thread, Transport packages, Collapse, Dynamics (Mechanics)

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NARROW

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

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

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

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

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

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

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

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

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

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

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

A Numerical Study on Fracture Toughness of CANDU Pressure Tube

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

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

Hydrogen Diffusion in FeCrAl Alloys for Light Water Reactors Cladding Applications

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

Geometrically-Accurate-Three-Dimensional Simulations of a Used Nuclear Fuel Canister Filled With Helium

Failure Criteria for Unirradiated PWR Cladding Subjected to Ring Compression Tests

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

Closure Bolt Modeling for Seal Evaluation Under Extreme Thermal Loads

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