1-20 of 260
Nuclear reactors
Close
Save search
Follow your search
Access your saved searches in your account
Would you like to receive an alert when new items match your search?
Close Modal
Sort by
Proceedings Papers

Fracture Toughness Tests on Western RPV Steels Using Small Scale Specimen Technique – Evaluation of Results

Florian Obermeier, Eberhard Altstadt, Hieronymus Hein, Aniruddh Das, Johannes May
Proc. ASME. PVP2024, Volume 1: Codes & Standards; Computer Technology & Bolted Joints, V001T01A059, July 28–August 2, 2024
Publisher: American Society of Mechanical Engineers
Paper No: PVP2024-122615
https://doi.org/10.1115/PVP2024-122615
View Paper titled, Fracture Toughness Tests on Western RPV Steels Using Small Scale Specimen Technique – Evaluation of Results
Open the PDF for Fracture Toughness Tests on Western RPV Steels Using Small Scale Specimen Technique – Evaluation of Results in another window
Topics: Fracture toughness, Steel, Fracture mechanics, Surveillance, Testing, Displacement, ASTM International, Cracking (Materials), Economics , Embrittlement
Proceedings Papers

Derivation of Input Distributions for Probabilistic Evaluation of PT/CT Contact in CANDU Reactors

Eric Nadeau, Adrian Baniak
Proc. ASME. PVP2024, Volume 2: Design & Analysis, V002T03A067, July 28–August 2, 2024
Publisher: American Society of Mechanical Engineers
Paper No: PVP2024-122832
https://doi.org/10.1115/PVP2024-122832
View Paper titled, Derivation of Input Distributions for Probabilistic Evaluation of PT/CT Contact in CANDU Reactors
Open the PDF for Derivation of Input Distributions for Probabilistic Evaluation of PT/CT Contact in CANDU Reactors in another window
Topics: Arches, Candu reactors, Cold climates, Cracking (Materials), Creep, Design, Fittings, Fracture (Materials), Fracture (Process), Fuels
Proceedings Papers

Computational Fluid Dynamics Approach to Evaluate Jet Impingement Loads Due to Rupture of High Energy Pipes in Nuclear Reactors

Ali M. M. I. Qureshy, M. Safy Hassan, Assem Elzaabalawy, Mohamed Aboulella, Qasim Khan, Waleed Mekky
Proc. ASME. PVP2024, Volume 3: Fluid-Structure Interaction; High Pressure Technology, V003T04A006, July 28–August 2, 2024
Publisher: American Society of Mechanical Engineers
Paper No: PVP2024-125095
https://doi.org/10.1115/PVP2024-125095
View Paper titled, Computational Fluid Dynamics Approach to Evaluate Jet Impingement Loads Due to Rupture of High Energy Pipes in Nuclear Reactors
Open the PDF for Computational Fluid Dynamics Approach to Evaluate Jet Impingement Loads Due to Rupture of High Energy Pipes in Nuclear Reactors in another window
Topics: Computational fluid dynamics, Nuclear reactors, Pipes, Rupture, Safety, Stress
Proceedings Papers

The Effects of Model Thickness on the Variation of Localised Stress Fields in Four-Point Bending Tests: A CPFE Study

Brandon Kuo, Masoud Taherijam, Hamidreza Abdolvand
Proc. ASME. PVP2024, Volume 4: Materials & Fabrication, V004T06A041, July 28–August 2, 2024
Publisher: American Society of Mechanical Engineers
Paper No: PVP2024-122917
https://doi.org/10.1115/PVP2024-122917
View Paper titled, The Effects of Model Thickness on the Variation of Localised Stress Fields in Four-Point Bending Tests: A CPFE Study
Open the PDF for The Effects of Model Thickness on the Variation of Localised Stress Fields in Four-Point Bending Tests: A CPFE Study in another window
Topics: Pressure, Stress, Zirconium, Electron backscatter diffraction, Hydrogen, Hydrostatics, Nuclear reactors, Atoms, Boundary-value problems, Crystals
Proceedings Papers

Life Prediction With Material Hardening Models for High Temperature Cyclic Loadings

Ryan McGuire, Ramesh Rajasekaran, Hsu-Kuang Ching, David Bankston, Jr.
Proc. ASME. PVP2024, Volume 4: Materials & Fabrication, V004T06A046, July 28–August 2, 2024
Publisher: American Society of Mechanical Engineers
Paper No: PVP2024-123509
https://doi.org/10.1115/PVP2024-123509
View Paper titled, Life Prediction With Material Hardening Models for High Temperature Cyclic Loadings
Open the PDF for Life Prediction With Material Hardening Models for High Temperature Cyclic Loadings in another window
Topics: Hardening, High temperature, Kinematics, Deformation, Reliability, Work hardening, Creep, Databases, Engineers, Inelastic analysis
Proceedings Papers

Physical Twins for Lifetime Evaluation of Safety-Relevant Large Components Containing Crack Fields

Linda Mally, Michael Seidenfuß, Martin Werz, Stefan Weihe
Proc. ASME. PVP2024, Volume 2: Design & Analysis, V002T03A107, July 28–August 2, 2024
Publisher: American Society of Mechanical Engineers
Paper No: PVP2024-123680
https://doi.org/10.1115/PVP2024-123680
View Paper titled, Physical Twins for Lifetime Evaluation of Safety-Relevant Large Components Containing Crack Fields
Open the PDF for Physical Twins for Lifetime Evaluation of Safety-Relevant Large Components Containing Crack Fields in another window
Topics: Additive manufacturing, Failure, Fracture (Materials), Safety, Testing, Lasers, Nuclear reactors, Pressure vessels, Shapes, Vessels
Proceedings Papers

A Methodology for Management of the Risk of Stress Corrosion Cracking of Cold Worked Austenitic Stainless Steels in Good Quality Water in Pressurised Water Reactor Plant

Joseph Malin, James Wilson, Timothy Watkins, Timothy Harrison, Benjamin Pellereau
Proc. ASME. PVP2023, Volume 2: Computer Technology & Bolted Joints; Design & Analysis, V002T03A024, July 16–21, 2023
Publisher: American Society of Mechanical Engineers
Paper No: PVP2023-108378
https://doi.org/10.1115/PVP2023-108378
View Paper titled, A Methodology for Management of the Risk of Stress Corrosion Cracking of Cold Worked Austenitic Stainless Steels in Good Quality Water in Pressurised Water Reactor Plant
Open the PDF for A Methodology for Management of the Risk of Stress Corrosion Cracking of Cold Worked Austenitic Stainless Steels in Good Quality Water in Pressurised Water Reactor Plant in another window
Topics: Risk, Stainless steel, Stress corrosion cracking, Water, Coolants, Circuits, Defense industry, Failure, Hydrogen, In-service inspection
Proceedings Papers

A Comprehensive Sample Problem for Section III Division 5 Design by Elastic Analysis

Bipul Barua, M. C. Messner
Proc. ASME. PVP2023, Volume 1: Codes & Standards, V001T01A061, July 16–21, 2023
Publisher: American Society of Mechanical Engineers
Paper No: PVP2023-107325
https://doi.org/10.1115/PVP2023-107325
View Paper titled, A Comprehensive Sample Problem for Section III Division 5 Design by Elastic Analysis
Open the PDF for A Comprehensive Sample Problem for Section III Division 5 Design by Elastic Analysis in another window
Topics: Design, Elastic analysis, Pressure vessels, Nozzles, Boilers, Breeder reactors, Carbon, Computer software, Finite element analysis, Heat
Proceedings Papers

Semi-Empirical Modeling of Irradiation-Induced Dimensional Change in H-451 Nuclear Graphite

Steve Johns, William E. Windes
Proc. ASME. PVP2023, Volume 1: Codes & Standards, V001T01A047, July 16–21, 2023
Publisher: American Society of Mechanical Engineers
Paper No: PVP2023-105209
https://doi.org/10.1115/PVP2023-105209
View Paper titled, Semi-Empirical Modeling of Irradiation-Induced Dimensional Change in H-451 Nuclear Graphite
Open the PDF for Semi-Empirical Modeling of Irradiation-Induced Dimensional Change in H-451 Nuclear Graphite in another window
Topics: Graphite, Irradiation (Radiation exposure), Modeling, Temperature, Molten salt reactors, Nuclear reactors, Atoms, Carbon, Design, Nonmetallic materials
Proceedings Papers

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

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
Open the PDF for Fractography of Neutron Irradiated RPV Steels – A Comparison of Shift in Reference Temperature and Net Hardening in another window
Topics: Fractography, Hardening, Neutrons, Steel, Temperature, Fracture (Materials), Irradiation (Radiation exposure), Embrittlement, Fracture toughness, Yield strength
Proceedings Papers

Statistical Approach to Developing a Performance Monitoring Program

David L. Rudland, Dan Widrevitz
Proc. ASME. PVP2023, Volume 1: Codes & Standards, V001T01A051, July 16–21, 2023
Publisher: American Society of Mechanical Engineers
Paper No: PVP2023-105203
https://doi.org/10.1115/PVP2023-105203
View Paper titled, Statistical Approach to Developing a Performance Monitoring Program
Open the PDF for Statistical Approach to Developing a Performance Monitoring Program in another window
Topics: In-service inspection, Inspection, Light water reactors, Nuclear reactors, Risk, Safety, Service life (Equipment)
Proceedings Papers

Fluid-Structure Interaction Simulations of a Rod Subjected to a Water Axial Flow in a Nuclear Core Relevant Configuration

Daniele Vivaldi, Roxan Pulicani
Proc. ASME. PVP2023, Volume 3: Fluid-Structure Interaction, V003T04A004, July 16–21, 2023
Publisher: American Society of Mechanical Engineers
Paper No: PVP2023-105808
https://doi.org/10.1115/PVP2023-105808
View Paper titled, Fluid-Structure Interaction Simulations of a Rod Subjected to a Water Axial Flow in a Nuclear Core Relevant Configuration
Open the PDF for Fluid-Structure Interaction Simulations of a Rod Subjected to a Water Axial Flow in a Nuclear Core Relevant Configuration in another window
Topics: Axial flow, Engineering simulation, Fluid structure interaction, Simulation, Water, Flow (Dynamics), Vibration, Computational fluid dynamics, Fluids, Turbulence
Proceedings Papers

Post Irradiation Examination of Pressurized Water Reactor Stainless Steel Internal Components

Timothy G. Lach, Xiang (Frank) Chen
Proc. ASME. PVP2023, Volume 5: Materials & Fabrication, V005T06A063, July 16–21, 2023
Publisher: American Society of Mechanical Engineers
Paper No: PVP2023-107347
https://doi.org/10.1115/PVP2023-107347
View Paper titled, Post Irradiation Examination of Pressurized Water Reactor Stainless Steel Internal Components
Open the PDF for Post Irradiation Examination of Pressurized Water Reactor Stainless Steel Internal Components in another window
Topics: Irradiation (Radiation exposure), Nuclear reactors, Pressurized water reactors, Stainless steel
Proceedings Papers

Advanced Structural Integrity Assessment Tools for Safe Long Term Operation (ATLAS+)

Sebastian Lindqvist, Anna Dahl, Mike Smith, Arnaud Blouin, Peter Dillström, Szabolcs Szavai, Tomas Nicak
Proc. ASME. PVP2022, Volume 4A: Materials and Fabrication, V04AT06A033, July 17–22, 2022
Publisher: American Society of Mechanical Engineers
Paper No: PVP2022-80693
https://doi.org/10.1115/PVP2022-80693
View Paper titled, Advanced Structural Integrity Assessment Tools for Safe Long Term Operation (ATLAS+)
Open the PDF for Advanced Structural Integrity Assessment Tools for Safe Long Term Operation (ATLAS+) in another window
Topics: Coolants, Fracture mechanics, Materials properties, Nuclear reactor coolants, Nuclear reactors, Piping systems, Pressure, Reactor vessels, Residual stresses, Safety
Proceedings Papers

ATLAS+ European Project - General Method for the Components J-R Curve Derivation

Tomas Nicak, Arnaud Blouin, Stephane Marie, Olivier Ancelet
Proc. ASME. PVP2022, Volume 4A: Materials and Fabrication, V04AT06A039, July 17–22, 2022
Publisher: American Society of Mechanical Engineers
Paper No: PVP2022-84853
https://doi.org/10.1115/PVP2022-84853
View Paper titled, ATLAS+ European Project - General Method for the Components J-R Curve Derivation
Open the PDF for ATLAS+ European Project - General Method for the Components J-R Curve Derivation in another window
Topics: Coolants, Fracture (Materials), Fracture mechanics, Geometry, Junctions, Materials properties, Nuclear reactors, Pipes, Pressure, Pressure vessels
Proceedings Papers

Advanced Structural Integrity Assessment Tools for Safe Long Term Operation - ATLAS+ Project: Status of the Activities of the WP3 on Modelling in 2020 & 2021

Arnaud Blouin, Stéphane Marie, Tomas Nicak, Antti Timperi, Peter Gill
Proc. ASME. PVP2022, Volume 4A: Materials and Fabrication, V04AT06A037, July 17–22, 2022
Publisher: American Society of Mechanical Engineers
Paper No: PVP2022-84842
https://doi.org/10.1115/PVP2022-84842
View Paper titled, Advanced Structural Integrity Assessment Tools for Safe Long Term Operation - ATLAS+ Project: Status of the Activities of the WP3 on Modelling in 2020 & 2021
Open the PDF for Advanced Structural Integrity Assessment Tools for Safe Long Term Operation - ATLAS+ Project: Status of the Activities of the WP3 on Modelling in 2020 & 2021 in another window
Topics: Coolants, Fracture (Materials), Fracture toughness, Leak-before-break, Modeling, Nuclear reactors, Pipes, Pressure, Residual stresses
Proceedings Papers

Ductile Tearing Prediction of Ferritic Pipes by GTN Model for ATLAS+ European Project (Report 2)

Satoshi Kumagai, Kiminobu Hojo, Takatoshi Hirota, Keiji Kawanishi
Proc. ASME. PVP2022, Volume 4A: Materials and Fabrication, V04AT06A036, July 17–22, 2022
Publisher: American Society of Mechanical Engineers
Paper No: PVP2022-84554
https://doi.org/10.1115/PVP2022-84554
View Paper titled, Ductile Tearing Prediction of Ferritic Pipes by GTN Model for ATLAS+ European Project (Report 2)
Open the PDF for Ductile Tearing Prediction of Ferritic Pipes by GTN Model for ATLAS+ European Project (Report 2) in another window
Topics: Ductile fracture, Finite element analysis, Pipes, Fracture (Materials), Coolants, Damage mechanics, Errors, Fracture mechanics, Nuclear reactors, Pressure
Proceedings Papers

Probabilistic Structural Integrity Analysis for Advanced Modular Reactors

James M. Finley, Henry Cathcart
Proc. ASME. PVP2022, Volume 1: Codes and Standards, V001T01A051, July 17–22, 2022
Publisher: American Society of Mechanical Engineers
Paper No: PVP2022-81135
https://doi.org/10.1115/PVP2022-81135
View Paper titled, Probabilistic Structural Integrity Analysis for Advanced Modular Reactors
Open the PDF for Probabilistic Structural Integrity Analysis for Advanced Modular Reactors in another window
Topics: Creep, Damage, Design, Emissions, High temperature, Nuclear reactors, Reliability, Robustness, Safety, Uncertainty
Proceedings Papers

Analysis to Relate Data From Radial Compression Tests on Helical Springs to Tensile Material Properties

Andre Gagnon, Donald Metzger
Proc. ASME. PVP2022, Volume 2: Computer Technology and Bolted Joints; Design and Analysis, V002T02A025, July 17–22, 2022
Publisher: American Society of Mechanical Engineers
Paper No: PVP2022-84892
https://doi.org/10.1115/PVP2022-84892
View Paper titled, Analysis to Relate Data From Radial Compression Tests on Helical Springs to Tensile Material Properties
Open the PDF for Analysis to Relate Data From Radial Compression Tests on Helical Springs to Tensile Material Properties in another window
Topics: Compression, Materials properties, Springs, Stress, Geometry, Dimensions, Failure, Bending (Stress), Displacement, Errors
Proceedings Papers

Design Charts for an Integrated Creep-Fatigue Damage Evaluation Approach

B. Barua, M. C. Messner, T.-L. Sham
Proc. ASME. PVP2022, Volume 1: Codes and Standards, V001T01A062, July 17–22, 2022
Publisher: American Society of Mechanical Engineers
Paper No: PVP2022-84807
https://doi.org/10.1115/PVP2022-84807
View Paper titled, Design Charts for an Integrated Creep-Fatigue Damage Evaluation Approach
Open the PDF for Design Charts for an Integrated Creep-Fatigue Damage Evaluation Approach in another window
Topics: Creep, Damage, Design, Fatigue, High temperature, Alloys, Design methodology, Failure data, Fatigue damage, Nuclear reactors