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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

DOI: https://doi.org/10.1115/PVP2022-84747

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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

Experimental Investigation of Jet Cross-Flow Induced Vibration of a Rod Bundle

Ibrahim Gad-el-Hak, Njuki Mureithi, Kostas Karazis, Gary Williams

Proc. ASME. PVP2021, Volume 3: Fluid Structure Interaction; High Pressure Technology, V003T04A014, July 13–15, 2021

Paper No: PVP2021-65000

DOI: https://doi.org/10.1115/PVP2021-65000

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Topics: Accidents, Coolants, Cross-flow, Fuel rods, Jets, Pressurized water reactors, Vibration

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

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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

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

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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

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

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

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Topics: Accidents, Fuels, Irradiation (Radiation exposure), Manufacturing, Testing, Cladding systems (Building), Pressurized water reactors, Transients (Dynamics), Design, Fuel systems

Proceedings Papers

Using Additive Manufacturing for Making Light Water Reactor Components

Raul B. Rebak, Xiaoyuan Lou

Proc. ASME. PVP2019, Volume 6B: Materials and Fabrication, V06BT06A011, July 14–19, 2019

Paper No: PVP2019-93129

DOI: https://doi.org/10.1115/PVP2019-93129

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Topics: Additive manufacturing, Light water reactors, Corrosion, Manufacturing, Cracking (Materials), Design, Electrochemical analysis, Failure mechanisms, Fracture (Process), Fuel rods

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

Effect of Clamping Failure on Flow Induced Vibration and Fretting Wear of Fuel Rods

Qi Huan-huan, Feng Zhi-peng, Xiong Fu-rui, Jiang Nai-bin, Huang Qian, Huang Xuan

Proc. ASME. PVP2018, Volume 4: Fluid-Structure Interaction, V004T04A001, July 15–20, 2018

Paper No: PVP2018-84326

DOI: https://doi.org/10.1115/PVP2018-84326

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Topics: Failure, Flow-induced vibrations, Fuel rods, Wear, Flow (Dynamics), Excitation, Pressurized water reactors, Turbulence, Displacement, Fuels

Proceedings Papers

Fatigue Behavior of Spent Nuclear Fuel Rods in Simulated Transportation Environment

Hong Wang, Jy-an John Wang, Hao Jiang

Proc. ASME. PVP2017, Volume 6B: Materials and Fabrication, V06BT06A026, July 16–20, 2017

Paper No: PVP2017-65842

DOI: https://doi.org/10.1115/PVP2017-65842

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Topics: Fatigue, Rods, Spent nuclear fuels, Transportation systems, Cladding systems (Building), Fuel rods, Storage, Fatigue life, Fuels, Irradiation (Radiation exposure)

Proceedings Papers

Fretting-Wear Damage due to Vibration in Nuclear and Process Equipment

Michel J. Pettigrew, Metin Yetisir, Nigel J. Fisher, Bruce A. W. Smith, Colette E. Taylor, Victor P. Janzen

Proc. ASME. PVP2017, Volume 4: Fluid-Structure Interaction, V004T04A032, July 16–20, 2017

Paper No: PVP2017-65272

DOI: https://doi.org/10.1115/PVP2017-65272

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Topics: Damage, Vibration, Wear, Fuel rods, Fuels, Heat exchangers, Pipes, Piping systems

Proceedings Papers

FeCrAl Alloys for Accident Tolerant Fuel Cladding in Light Water Reactors

Raul B. Rebak, Kurt A. Terrani, Russ M. Fawcett

Proc. ASME. PVP2016, Volume 6B: Materials and Fabrication, V06BT06A009, July 17–21, 2016

Paper No: PVP2016-63162

DOI: https://doi.org/10.1115/PVP2016-63162

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Topics: Accidents, Alloys, Cladding systems (Building), Fuels, Light water reactors, Fuel systems, Manufacturing, Aluminum, Cooling, Design

Proceedings Papers

Anticipated Improved Performance of Advanced Steel Cladding Under Long Term Dry Storage of Spent Fuel

Raul B. Rebak, Shenyan Huang

Proc. ASME. PVP2015, Volume 7: Operations, Applications and Components, V007T07A042, July 19–23, 2015

Paper No: PVP2015-45643

DOI: https://doi.org/10.1115/PVP2015-45643

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Topics: Cladding systems (Building), Spent nuclear fuels, Steel, Storage, Fuels, Zirconium alloys, Accidents, Alloys, Delays, Fuel rods

Proceedings Papers

Flaw Effects and Flaw Reorientation on Spent Fuel Rod Performance: A Simulation With Finite Element Analysis

David T. Tang, Antonio Rigato, Robert Einziger

Proc. ASME. PVP2015, Volume 7: Operations, Applications and Components, V007T07A039, July 19–23, 2015

Paper No: PVP2015-45306

DOI: https://doi.org/10.1115/PVP2015-45306

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Topics: Finite element analysis, Simulation, Spent nuclear fuels, Fuels, Cladding systems (Building), Bending strength, Drying, Failure, Fracture (Materials), Fuel rods

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

Paper No: PVP2015-45947

DOI: https://doi.org/10.1115/PVP2015-45947

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Topics: Cladding systems (Building), Engineering prototypes, Explosives, Fuel rods, Fuels, Heat, Helium, Hydrogen, Nuclear fuels, Oxidation

Proceedings Papers

Comparison of Ring Compression Testing to Three Point Bend Testing for Unirradiated ZIRLO Cladding

Paul S. Korinko, Robert L. Sindelar, Ronald L. Kesterson

Proc. ASME. PVP2015, Volume 7: Operations, Applications and Components, V007T07A055, July 19–23, 2015

Paper No: PVP2015-45984

DOI: https://doi.org/10.1115/PVP2015-45984

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Topics: Cladding systems (Building), Compression, Testing, Hydrogen, Accidents, Fuels, Temperature, Drying, Storage, Containers

Proceedings Papers

Fabrication, Welding, and Inspection Techniques in Preparation for In-Reactor Testing of Accident Tolerant Fuels

Kristine Barrett, Michael Teague, Glenn Moore, Connor Woolum, Kip Archibald

Proc. ASME. PVP2015, Volume 6A: Materials and Fabrication, V06AT06A002, July 19–23, 2015

Paper No: PVP2015-45675

DOI: https://doi.org/10.1115/PVP2015-45675

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Topics: Accidents, Fuels, Inspection, Manufacturing, Testing, Welding, Cladding systems (Building), Light water reactors, Design, Irradiation (Radiation exposure)

Proceedings Papers

Identification of the Turbulence Force Field Excitation From a Set of Vibratory Responses of a Multi-Supported Tube

Jose Antunes, Laurent Borsoi, Xavier Delaune, Philippe Piteau

Proc. ASME. PVP2013, Volume 4: Fluid-Structure Interaction, V004T04A062, July 14–18, 2013

Paper No: PVP2013-98146

DOI: https://doi.org/10.1115/PVP2013-98146

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Topics: Excitation, Turbulence, Spectra (Spectroscopy), Flow (Dynamics), Boilers, Computer simulation, Fittings, Fuel rods

Proceedings Papers

Mechanical Behaviour of High Burn-Up SNF Under Normal and Accident Transport Conditions: Present Approaches and Perspectives

Viktor Ballheimer, Frank Wille, Annette Rolle, Bernhard Droste

Proc. ASME. PVP2012, Volume 7: Operations, Applications and Components, 229-235, July 15–19, 2012

Paper No: PVP2012-78302

DOI: https://doi.org/10.1115/PVP2012-78302

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Topics: Accidents, Mechanical behavior, Fuels, Spent nuclear fuels, Fuel rods, Cladding systems (Building), Safety, Containment, Failure mechanisms, Fracture (Materials)

Proceedings Papers

CFD Analyses of the TN-24P PWR Spent Fuel Storage Cask

Robert A. Brewster, Emilio Baglietto, Eric Volpenhein, Christopher S. Bajwa

Proc. ASME. PVP2012, Volume 3: Design and Analysis, 17-25, July 15–19, 2012

Paper No: PVP2012-78491

DOI: https://doi.org/10.1115/PVP2012-78491

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Topics: Computational fluid dynamics, Pressurized water reactors, Spent fuel storage, Spent nuclear fuels, Fuels, Porous materials, Storage, Temperature, Cladding systems (Building), Computer software

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NARROW

Large-Scale Parametric Modeling of Spent Nuclear Fuel Dynamics in the 30 cm Package Drop Scenario

Experimental Investigation of Jet Cross-Flow Induced Vibration of a Rod Bundle

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

30 CM Horizontal Drop of a Surrogate 17x17 PWR Fuel Assembly

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

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

Using Additive Manufacturing for Making Light Water Reactor Components

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

Effect of Clamping Failure on Flow Induced Vibration and Fretting Wear of Fuel Rods

Fatigue Behavior of Spent Nuclear Fuel Rods in Simulated Transportation Environment

Fretting-Wear Damage due to Vibration in Nuclear and Process Equipment

FeCrAl Alloys for Accident Tolerant Fuel Cladding in Light Water Reactors

Anticipated Improved Performance of Advanced Steel Cladding Under Long Term Dry Storage of Spent Fuel

Flaw Effects and Flaw Reorientation on Spent Fuel Rod Performance: A Simulation With Finite Element Analysis

Monitoring Helium Integrity in Welded Canisters

Comparison of Ring Compression Testing to Three Point Bend Testing for Unirradiated ZIRLO Cladding

Fabrication, Welding, and Inspection Techniques in Preparation for In-Reactor Testing of Accident Tolerant Fuels

Identification of the Turbulence Force Field Excitation From a Set of Vibratory Responses of a Multi-Supported Tube

Mechanical Behaviour of High Burn-Up SNF Under Normal and Accident Transport Conditions: Present Approaches and Perspectives

CFD Analyses of the TN-24P PWR Spent Fuel Storage Cask

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