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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

DOI: https://doi.org/10.1115/PVP2021-61608

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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

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

Auxiliary Beam Stress Improved Laser Welding for Repair of Irradiated Light Water Reactor Components

Jian Chen, Jonathan Tatman, Zhili Feng, Roger Miller, Wei Tang, Maxim Gussev, Keith Leonard, Benjamin Sutton, Greg Frederick

Proc. ASME. PVP2019, Volume 1: Codes and Standards, V001T01A093, July 14–19, 2019

Paper No: PVP2019-93667

DOI: https://doi.org/10.1115/PVP2019-93667

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Topics: Laser welding, Light water reactors, Maintenance, Stress, Welding, Nuclear reactors, Compression, Computer simulation, Cooling, Cracking (Materials)

Proceedings Papers

Hot Cell Pulsed Laser Welding of Neutron Irradiated Type 304 Stainless Steel With a Maximum Damage Dose of 28 DPA

Paula D. Freyer, Jonathan K. Tatman, Frank A. Garner, Greg J. Frederick, Benjamin J. Sutton

Proc. ASME. PVP2019, Volume 1: Codes and Standards, V001T01A087, July 14–19, 2019

Paper No: PVP2019-93316

DOI: https://doi.org/10.1115/PVP2019-93316

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Topics: Damage, Laser welding, Neutrons, Stainless steel, Helium, Welding, Heat, Welded joints, Cracking (Materials), Fracture (Process)

Proceedings Papers

Analysis of EDS Vessel Clamping System and Door Seal

Jerome H. Stofleth, Megan K. Tribble, John Ludwigsen, Robert W. Crocker

Proc. ASME. PVP2019, Volume 5: High-Pressure Technology; Rudy Scavuzzo Student Paper Symposium and 27th Annual Student Paper Competition; ASME Nondestructive Evaluation, Diagnosis and Prognosis Division (NDPD), V005T05A025, July 14–19, 2019

Paper No: PVP2019-93755

DOI: https://doi.org/10.1115/PVP2019-93755

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Topics: Doors, Vessels, Explosives, Metals, Explosions, Containment vessels, Flanges, Forging, Gaskets, Stainless steel

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

Effect of Hydrogen Isotopes on the Fracture Toughness Properties of Types 316L and 304L Stainless Steel Forgings

Michael J. Morgan

Proc. ASME. PVP2019, Volume 6B: Materials and Fabrication, V06BT06A033, July 14–19, 2019

Paper No: PVP2019-93702

DOI: https://doi.org/10.1115/PVP2019-93702

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Topics: Forgings (Products), Fracture toughness, Hydrogen, Isotopes, Stainless steel, Forging, Yield strength, Helium, Alpha decay, Containment

Proceedings Papers

Evaluation of Welding Techniques for Stainless Steels Piping Without Use of Backing Gas

Siva Kumar Chiluvuri, Kevin Bliss, Jorge Penso

Proc. ASME. PVP2019, Volume 6B: Materials and Fabrication, V06BT06A004, July 14–19, 2019

Paper No: PVP2019-93359

DOI: https://doi.org/10.1115/PVP2019-93359

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Topics: Pipes, Stainless steel, Welding, Gas tungsten arc welding, Safety, Alloy steel, Construction, Construction industry, Hazards, Helium

Proceedings Papers

The Use of Different Media in Leakage Tests

Manfred Schaaf, Frank Herkert, Adam Arnett

Proc. ASME. PVP2019, Volume 2: Computer Technology and Bolted Joints, V002T02A022, July 14–19, 2019

Paper No: PVP2019-93531

DOI: https://doi.org/10.1115/PVP2019-93531

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Topics: Helium, Leakage, Mass spectrometers, Methane, Nitrogen, Testing performance

Proceedings Papers

Prediction of Liquid and Gas Leak Rates in Packed Stuffing Boxes

Ali Salah Omar Aweimer, Abdel-Hakim Bouzid

Proc. ASME. PVP2019, Volume 2: Computer Technology and Bolted Joints, V002T02A018, July 14–19, 2019

Paper No: PVP2019-93001

DOI: https://doi.org/10.1115/PVP2019-93001

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Topics: Flow (Dynamics), Leakage, Stress, Packings (Cushioning), Helium, Porosity, Analytical methods, Boundary-value problems, Compressible flow, Experimental methods

Proceedings Papers

A Compendium of Mechanical Testing of Austenitic Stainless Steels in Hydrogen

Poh-Sang Lam, Andrew J. Duncan, Michael J. Morgan, Robert L. Sindelar, Thad M. Adams

Proc. ASME. PVP2018, Volume 1A: Codes and Standards, V01AT01A040, July 15–20, 2018

Paper No: PVP2018-84723

DOI: https://doi.org/10.1115/PVP2018-84723

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Topics: Hydrogen, Mechanical testing, Stainless steel, Ductility, Grain size, Nickel, Rivers, High pressure (Physics), Alloys, Elongation

Proceedings Papers

Hydrogen Transfer Line Structural Analysis

Peter M. Rosenblad, L. P. Buchanan, C. R. Bett

Proc. ASME. PVP2018, Volume 3A: Design and Analysis, V03AT03A021, July 15–20, 2018

Paper No: PVP2018-84061

DOI: https://doi.org/10.1115/PVP2018-84061

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Topics: Hydrogen, Structural analysis, Vacuum, Design, Tubing, Containment, Neutron beams, Vessels, Dynamic analysis, Earthquakes

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

Influence of 70 MPa Hydrogen Gas on SUS 630 From 77 K to 373 K by Simple Testing Method

Toshio Ogata

Proc. ASME. PVP2018, Volume 6B: Materials and Fabrication, V06BT06A035, July 15–20, 2018

Paper No: PVP2018-84462

DOI: https://doi.org/10.1115/PVP2018-84462

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Topics: Hydrogen, Testing, Helium, Pressure, Stress, Embrittlement, Tensile strength

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

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

Repair Welding of Irradiated Reactor Pressure Vessels Steel and Current Direction of Revising JSME Fitness-for-Service Code

Hiroyuki Adachi, Ryuji Kimura, Yusuke Kono

Proc. ASME. PVP2017, Volume 1B: Codes and Standards, V01BT01A055, July 16–20, 2017

Paper No: PVP2017-65659

DOI: https://doi.org/10.1115/PVP2017-65659

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Topics: Fitness-for-service, Japan Society of Mechanical Engineers, Maintenance, Reactor vessels, Steel, Welding, Helium, Light water reactors, Neutrons, ASME Standards

Proceedings Papers

Proactive In-Situ Welding Stress Control for Laser Repair Welding of Irradiated Austenitic Materials

Jian Chen, Jonathan Tatman, Zongyao Chen, Zhili Feng, Greg Frederick

Proc. ASME. PVP2017, Volume 6B: Materials and Fabrication, V06BT06A020, July 16–20, 2017

Paper No: PVP2017-65202

DOI: https://doi.org/10.1115/PVP2017-65202

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Topics: Lasers, Maintenance, Stress, Welding, Computer simulation, Light water reactors, Cracking (Materials), Fracture (Process), Helium, Compressive stress

2 3 4 5

NARROW

Thermal Stress Analysis of a Spent Nuclear Fuel Canister

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

Auxiliary Beam Stress Improved Laser Welding for Repair of Irradiated Light Water Reactor Components

Hot Cell Pulsed Laser Welding of Neutron Irradiated Type 304 Stainless Steel With a Maximum Damage Dose of 28 DPA

Analysis of EDS Vessel Clamping System and Door Seal

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

Effect of Hydrogen Isotopes on the Fracture Toughness Properties of Types 316L and 304L Stainless Steel Forgings

Evaluation of Welding Techniques for Stainless Steels Piping Without Use of Backing Gas

The Use of Different Media in Leakage Tests

Prediction of Liquid and Gas Leak Rates in Packed Stuffing Boxes

A Compendium of Mechanical Testing of Austenitic Stainless Steels in Hydrogen

Hydrogen Transfer Line Structural Analysis

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

Influence of 70 MPa Hydrogen Gas on SUS 630 From 77 K to 373 K by Simple Testing Method

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

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

Repair Welding of Irradiated Reactor Pressure Vessels Steel and Current Direction of Revising JSME Fitness-for-Service Code

Proactive In-Situ Welding Stress Control for Laser Repair Welding of Irradiated Austenitic Materials

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