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Proceedings Papers

Preliminary Investigation of the Effects of Neutron Irradiation on the Weibull Modulus of Graphite

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Anne A. Campbell
Proc. ASME. PVP2024, Volume 1: Codes & Standards; Computer Technology & Bolted Joints, V001T01A039, July 28–August 2, 2024
Publisher: American Society of Mechanical Engineers
Paper No: PVP2024-122371
https://doi.org/10.1115/PVP2024-122371
View Paper titled, Preliminary Investigation of the Effects of Neutron Irradiation on the Weibull Modulus of Graphite
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Topics: Graphite, Irradiation (Radiation exposure), Neutrons
Proceedings Papers

Nuclear Graphite Irradiated Material Property Normalization, Interpolation, and Extrapolation Approach

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Adam Walker, Kevin Caldwell, Stuart Kellner, Anthony Schroeder
Proc. ASME. PVP2024, Volume 1: Codes & Standards; Computer Technology & Bolted Joints, V001T01A043, July 28–August 2, 2024
Publisher: American Society of Mechanical Engineers
Paper No: PVP2024-123523
https://doi.org/10.1115/PVP2024-123523
View Paper titled, Nuclear Graphite Irradiated Material Property Normalization, Interpolation, and Extrapolation Approach
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Topics: Fluence (Radiation measurement), Graphite, Interpolation, Materials properties, Neutrons
Proceedings Papers

Assessment of the Need to Consider HAZ Properties as Part of RPV Integrity Management

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Mark Kirk, Marjorie Erickson, Elliot J. Long
Proc. ASME. PVP2023, Volume 1: Codes & Standards, V001T01A033, July 16–21, 2023
Publisher: American Society of Mechanical Engineers
Paper No: PVP2023-105904
https://doi.org/10.1115/PVP2023-105904
View Paper titled, Assessment of the Need to Consider HAZ Properties as Part of RPV Integrity Management
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Topics: ASME Standards, Base metals, Electromagnetic scattering, Embrittlement, Fracture toughness, Heat, Irradiation (Radiation exposure), Metals, Neutrons, Phase transition temperature
Proceedings Papers

Fractography of Neutron Irradiated RPV Steels – A Comparison of Shift in Reference Temperature and Net Hardening

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Aniruddh Das, Paul Chekhonin, Mario Houska, Florian Obermeier, Eberhard Altstadt
Proc. ASME. PVP2023, Volume 1: Codes & Standards, V001T01A028, July 16–21, 2023
Publisher: American Society of Mechanical Engineers
Paper No: PVP2023-103648
https://doi.org/10.1115/PVP2023-103648
View Paper titled, Fractography of Neutron Irradiated RPV Steels – A Comparison of Shift in Reference Temperature and Net Hardening
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Topics: Fractography, Hardening, Neutrons, Steel, Temperature, Fracture (Materials), Irradiation (Radiation exposure), Embrittlement, Fracture toughness, Yield strength
Proceedings Papers

NeT Project Task Group 8 – An International Benchmark on Residual Stress Assessment for Welding Repair

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Vincent Robin, Jefri Draup, Sofiane Hendili, Josselin Delmas, Qingrong Xiong, Mike Smith, Alexandre Paget
Proc. ASME. PVP2022, Volume 4B: Materials and Fabrication, V04BT06A058, July 17–22, 2022
Publisher: American Society of Mechanical Engineers
Paper No: PVP2022-85083
https://doi.org/10.1115/PVP2022-85083
View Paper titled, NeT Project Task Group 8 – An International Benchmark on Residual Stress Assessment for Welding Repair
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Topics: Maintenance, Project tasks, Stress, Welding, Alloys, Modeling, Welded joints, Materials characterization, Neutrons, Residual stresses
Proceedings Papers

Finite Element Analysis of Outer Pressure Containment Vessel and Proton Beam Pipe for Proton Radiography Under Operational Loads

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Ryan Holguin, Dallas Hill, Heidi Reichert, Kyle Deines, Gerald Bustos
Proc. ASME. PVP2022, Volume 2: Computer Technology and Bolted Joints; Design and Analysis, V002T03A029, July 17–22, 2022
Publisher: American Society of Mechanical Engineers
Paper No: PVP2022-83987
https://doi.org/10.1115/PVP2022-83987
View Paper titled, Finite Element Analysis of Outer Pressure Containment Vessel and Proton Beam Pipe for Proton Radiography Under Operational Loads
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Topics: Containment vessels, Finite element analysis, Pipes, Pressure, Proton beams, Protons, Stress, ASME Boiler and Pressure Vessel Code, Bellows (Equipment), Containment
Proceedings Papers

FRACTESUS Project: Final Selection of RPV Materials for Unirradiated and Irradiated Round Robins

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Tomasz Brynk, Inge Uytdenhouwen, Pentti Arffman, Eberhard Altstadt, Radim Kopriva, Florian Obermeier, Marta Serrano
Proc. ASME. PVP2022, Volume 1: Codes and Standards, V001T01A026, July 17–22, 2022
Publisher: American Society of Mechanical Engineers
Paper No: PVP2022-83871
https://doi.org/10.1115/PVP2022-83871
View Paper titled, FRACTESUS Project: Final Selection of RPV Materials for Unirradiated and Irradiated Round Robins
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Topics: Base metals, Databases, Fracture toughness, Irradiation (Radiation exposure), Mechanical properties, Neutrons, Notch testing, Reactor vessels, Temperature, Tension
Proceedings Papers

Probabilistic Control Rod Failure Analysis for a Nominal Molten Salt Reactor

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Henry Cathcart, James Finley, John Taylor, Alexander Frost
Proc. ASME. PVP2022, Volume 1: Codes and Standards, V001T01A055, July 17–22, 2022
Publisher: American Society of Mechanical Engineers
Paper No: PVP2022-84742
https://doi.org/10.1115/PVP2022-84742
View Paper titled, Probabilistic Control Rod Failure Analysis for a Nominal Molten Salt Reactor
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Topics: Atoms, Bricks, Carbon, Dimensions, Emissions, Failure, Failure analysis, Finite element analysis, Fluence (Radiation measurement), Fuels
Proceedings Papers

Coupling of Neutron Noise and Dynamic Finite Element Analyses to Perform Remote Condition Monitoring for Reactor Vessel Internals

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Gregory A. Banyay, Matthew J. Palamara, Stephen D. Smith
Proc. ASME. PVP2021, Volume 3: Fluid Structure Interaction; High Pressure Technology, V003T04A006, July 13–15, 2021
Publisher: American Society of Mechanical Engineers
Paper No: PVP2021-62201
https://doi.org/10.1115/PVP2021-62201
View Paper titled, Coupling of Neutron Noise and Dynamic Finite Element Analyses to Perform Remote Condition Monitoring for Reactor Vessel Internals
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Topics: Condition monitoring, Finite element analysis, Heat shielding, Machine learning, Neutrons, Noise (Sound), Reactor vessels, Structural dynamics, Structural health monitoring
Proceedings Papers

Effect of Neutron Irradiation on the Mechanical Properties of an A508 CL2 and 15Kh2NMFA Irradiated in the NOMAD_3 Rig in the BR2 Cooling Water

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Inge Uytdenhouwen, Rachid Chaouadi
Proc. ASME. PVP2021, Volume 1: Codes and Standards, V001T01A024, July 13–15, 2021
Publisher: American Society of Mechanical Engineers
Paper No: PVP2021-61969
https://doi.org/10.1115/PVP2021-61969
View Paper titled, Effect of Neutron Irradiation on the Mechanical Properties of an A508 CL2 and 15Kh2NMFA Irradiated in the NOMAD_3 Rig in the BR2 Cooling Water
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Topics: Cooling, Irradiation (Radiation exposure), Mechanical properties, Neutrons, Water
Proceedings Papers

Fracture Toughness in Postulated Crack Area of PTS Evaluation in Highly-Neutron Irradiated RPV Steel

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Yoosung Ha, Masaki Shimodaira, Hisashi Takamizawa, Tohru Tobita, Jinya Katsuyama, Yutaka Nishiyama
Proc. ASME. PVP2021, Volume 1: Codes and Standards, V001T01A058, July 13–15, 2021
Publisher: American Society of Mechanical Engineers
Paper No: PVP2021-61892
https://doi.org/10.1115/PVP2021-61892
View Paper titled, Fracture Toughness in Postulated Crack Area of PTS Evaluation in Highly-Neutron Irradiated RPV Steel
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Topics: Fracture (Materials), Fracture toughness, Heat, Neutrons, Steel, Vickers hardness testing
Proceedings Papers

NuScale Pressure and Temperature Limits Methodology Using Finite Element Analysis

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Heqin Xu, Joe Remic, Hongqing Xu
Proc. ASME. PVP2021, Volume 2: Computer Technology and Bolted Joints; Design and Analysis, V002T03A018, July 13–15, 2021
Publisher: American Society of Mechanical Engineers
Paper No: PVP2021-61856
https://doi.org/10.1115/PVP2021-61856
View Paper titled, NuScale Pressure and Temperature Limits Methodology Using Finite Element Analysis
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Topics: Finite element analysis, Fracture mechanics, Pressure, Temperature, Brittleness, Cylinders, Design, Ductility, Failure, Finite element model
Proceedings Papers

Applicability of Formula of the Irradiation Assisted Stress Corrosion Cracking Rates for Neutron-Irradiated Type 316L Stainless Steels to Various Types of Stainless Steels Under Boiling Water Reactor Condition

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Masato Koshiishi, Hitoshi Seto, Shigeaki Tanaka, Ryoji Obata
Proc. ASME. PVP2020, Volume 6: Materials and Fabrication, V006T06A073, August 3, 2020
Publisher: American Society of Mechanical Engineers
Paper No: PVP2020-21332
https://doi.org/10.1115/PVP2020-21332
View Paper titled, Applicability of Formula of the Irradiation Assisted Stress Corrosion Cracking Rates for Neutron-Irradiated Type 316L Stainless Steels to Various Types of Stainless Steels Under Boiling Water Reactor Condition
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Topics: Boiling water reactors, Irradiation (Radiation exposure), Neutrons, Stainless steel, Stress corrosion cracking, Fracture (Materials), Grain boundaries, Mechanical properties
Proceedings Papers

An Investigation Into the Robustness of a Crystal Plasticity Finite Element Model

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Megan Taylor, Dylan Agius, David Knowles, Mahmoud Mostafavi
Proc. ASME. PVP2020, Volume 6: Materials and Fabrication, V006T06A094, August 3, 2020
Publisher: American Society of Mechanical Engineers
Paper No: PVP2020-21746
https://doi.org/10.1115/PVP2020-21746
View Paper titled, An Investigation Into the Robustness of a Crystal Plasticity Finite Element Model
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Topics: Crystals, Finite element model, Plasticity, Robustness, Boundary-value problems, Stress, Diffraction, Simulation, Deformation, Displacement
Proceedings Papers

Estimation of Charpy Index Temperature of SA 508 Mn-Mo-Ni Low Alloy Steels at 41J Using Small Punch Tests

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Jongmin Kim, Seokmin Hong, Taekyoung Lee, Minchul Kim
Proc. ASME. PVP2020, Volume 6: Materials and Fabrication, V006T06A074, August 3, 2020
Publisher: American Society of Mechanical Engineers
Paper No: PVP2020-21360
https://doi.org/10.1115/PVP2020-21360
View Paper titled, Estimation of Charpy Index Temperature of SA 508 Mn-Mo-Ni Low Alloy Steels at 41J Using Small Punch Tests
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Topics: Alloy steel, Temperature, Displacement, Fracture (Materials), Fracture (Process), Fracture toughness, Stress, Failure mechanisms, Irradiation (Radiation exposure), Mechanical properties
Proceedings Papers

Evaluation of Crack Growth Rate of Neutron Irradiated Austenitic Stainless Steels at High Stress Intensity Factor Levels

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Hitoshi Seto, Masato Koshiishi, Shigeaki Tanaka, Ryoji Obata
Proc. ASME. PVP2020, Volume 6: Materials and Fabrication, V006T06A075, August 3, 2020
Publisher: American Society of Mechanical Engineers
Paper No: PVP2020-21365
https://doi.org/10.1115/PVP2020-21365
View Paper titled, Evaluation of Crack Growth Rate of Neutron Irradiated Austenitic Stainless Steels at High Stress Intensity Factor Levels
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Topics: Fracture (Materials), Neutrons, Stainless steel, Stress
Proceedings Papers

Comparison of Residual Stress Measurements on Single Bead-on-Plate Welds of a Martensitic Steel Using Neutron Diffraction

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Spyridon A. Alexandratos, Robert C. Wimpory, Tung-Lik Lee, Padraig Mac Ardghail, Sean B. Leen, Noel P. O’Dowd
Proc. ASME. PVP2020, Volume 6: Materials and Fabrication, V006T06A114, August 3, 2020
Publisher: American Society of Mechanical Engineers
Paper No: PVP2020-21776
https://doi.org/10.1115/PVP2020-21776
View Paper titled, Comparison of Residual Stress Measurements on Single Bead-on-Plate Welds of a Martensitic Steel Using Neutron Diffraction
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Topics: Martensitic steel, Neutron diffraction, Stress, Welded joints, Instrumentation, Neutrons, Stress concentration, Welding, Base metals, Cycles
Proceedings Papers

NOMAD: Non-Destructive Evaluation (NDE) System for the Inspection of Operation-Induced Material Degradation in Nuclear Power Plants — Overview of the Neutron Irradiation Campaigns

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Inge Uytdenhouwen, Rachid Chaouadi
Proc. ASME. PVP2020, Volume 7: Non-Destructive Examination, V007T07A003, August 3, 2020
Publisher: American Society of Mechanical Engineers
Paper No: PVP2020-21512
https://doi.org/10.1115/PVP2020-21512
View Paper titled, NOMAD: Non-Destructive Evaluation (NDE) System for the Inspection of Operation-Induced Material Degradation in Nuclear Power Plants — Overview of the Neutron Irradiation Campaigns
Open the PDF for NOMAD: Non-Destructive Evaluation (NDE) System for the Inspection of Operation-Induced Material Degradation in Nuclear Power Plants — Overview of the Neutron Irradiation Campaigns in another window
Topics: Inspection, Irradiation (Radiation exposure), Materials degradation, Neutrons, Nondestructive evaluation, Nuclear power stations
Proceedings Papers

Fracture Mechanics Assessment of Reactor Pressure Vessel Irradiated Structural Steel for Short Column Type Supports and Neutron Shield Tank

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Alexandria M. Carolan, J. Brian Hall, Stephen K. Longwell, F. Arzu Alpan, Gregory M. Imbrogno, Anees A. Udyawar, Scott Boggs, Steve Franzone, Charles Tomes, Beth Haluska
Proc. ASME. PVP2020, Volume 6: Materials and Fabrication, V006T06A007, August 3, 2020
Publisher: American Society of Mechanical Engineers
Paper No: PVP2020-21142
https://doi.org/10.1115/PVP2020-21142
View Paper titled, Fracture Mechanics Assessment of Reactor Pressure Vessel Irradiated Structural Steel for Short Column Type Supports and Neutron Shield Tank
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Topics: Fracture mechanics, Neutrons, Reactor vessels, Structural steel
Proceedings Papers

Effect of Neutron Irradiation on the Mechanical Properties of an A508 Cl.2 Forging Irradiated in a BAMI Capsule

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Inge Uytdenhouwen, Rachid Chaouadi
Proc. ASME. PVP2020, Volume 1: Codes and Standards, V001T01A060, August 3, 2020
Publisher: American Society of Mechanical Engineers
Paper No: PVP2020-21513
https://doi.org/10.1115/PVP2020-21513
View Paper titled, Effect of Neutron Irradiation on the Mechanical Properties of an A508 Cl.2 Forging Irradiated in a BAMI Capsule
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Topics: Forging, Fracture toughness, Irradiation (Radiation exposure), Mechanical properties, Neutrons