NDLI: Management of Complex Loading Histories for Use in Probabilistic Creep-Fatigue Damage Assessments

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Volume 1B: Codes and Standards

Management of Complex Loading Histories for Use in Probabilistic Creep-Fatigue Damage Assessments

Effects of Non-Normal Input Distributions and Sampling Region on Monte Carlo Results

Development of Probabilistic Fracture Mechanics Analysis Code PASCAL Version 4 for Reactor Pressure Vessels

Acceptance Criteria for Probabilistic Fracture Protection Evaluations of CANDU Zr-Nb Pressure Tubes

A Treatise on Weld Evaluation

Inter-Laboratory Proficiency Testing of NDT Labs According to ISO 17043 As a Tool for Continuous Improvement Principle According to ISO 9001

ASME ANDE-1: A Completely New Approach to Personnel Qualification

2025 Nuclear Code: The Vision for the Future of ASME Nuclear Codes and Standards

Pressure Temperature Ratings of Aluminum Alloy Flanges

Technical Basis for Proposed Fifth Revision to ASME Code Case N-513

The Role of Material Modeling on Strain Range Estimation for Elevated Temperature Cyclic Life Evaluation

The Mechanical Interaction of Clad and Base Metal for Molten Salt Reactor Structural Components

Detection of Ratcheting in Finite Element Calculations

A Basis for Applying Elastic Perfectly-Plastic Design Methods to Cyclic Softening Materials

A Unified Inelastic Constitutive Model for the Average Engineering Response of Grade 91 Steel

Establishing Temperature Upper Limits for the ASME Section III, Division 5 Design by Elastic Analysis Methods

N-Bar Problems As Approximations to the Bree Problem

Assessment of Passively Actuated In-Situ Cyclic Surveillance Test Specimens for Advanced Non-Light Water Reactors

Anisotropic Materials Use in the ASME Boiler and Pressure Vessel Code

Buckling of Tanks With a Conical Roof Under Harmonic Settlement

Consideration of Pressure Vessels Codes and Standards for Fire Emergency Rescue in China: Now and Future

Fracture Failure Analysis of 304 Stainless Steel Elbow

Development of Lightweight Design and Manufacture of Heavy-Duty Pressure Vessels in China

Research on Phased Array Ultrasonic Testing for the Girth Weld of 4mm~10mm Austenitic Stainless Steel Pipeline

Erosion-Corrosion of a Carbon Steel Elbow in a Natural Gas Gathering Pipeline

Creep Analysis for Pressurized Components Under Creep Conditions Based on Isochronous Stress-Strain Curve and Elastic-Perfectly Plastic Material Model

Development of Small Diameter and Thin-Walled Tube Docking Girth Joint Ultrasonic Testing Probe and Block

The Notched C-Ring Test to Evaluate Reheat Cracking Susceptibility of CGHAZ in 2¼Cr-1Mo-¼V Steel Welded Joints

Case Study of Nonlinear Buckling With Shape Distortion due to Thermal Load

Experimental Investigation of Post-Fire Mechanical Properties of Quenched and Tempered High Strength Steel 07MnMoVR

Experimental Study on Mechanical Properties and Microstructure of 2.25Cr1Mo0.25V Steel by the Influence of Heat Treatment and Welding

Light-Weight Mechanism of Pressure Strengthening of Cryogenic Vessels From Austenitic Stainless Steel

A Study on Damping Ratio in the Design Code of Vertical Vessels Supported by Skirt

Study on the Response Behavior of Large Steel Seamless Cylinder Pressure Relief Devices Under Different Fire Conditions

Investigation on Fluid Induced Vibration of Heat Exchanger Beyond Pitch Ratio Range in TEMA Standards and GB/T 151

The Research on Automatic Defect Recognition for Phased Array Ultrasonic Inspection of Polyolefin Butt Thermal-Fusion Joint

Low-Cycled Fatigue Life of S30408 Stainless Steel at Liquid-Nitrogen Temperature

Study on the Risk Based Inspection and Evaluation System for Polyethylene Gas Pipeline

Finite Element Analysis for Failure of Dividing Wall of MMDI Distillation Column

Research and Application of Ultrasonic Guided Wave With L(0,2) Mode for Elbow Tube Defect Inspection

Research on Reheat Cracking Criterion of CGHAZ in 2.25Cr1Mo0.25V Steel

Investigation on Standards on Hydrogen Cycle of Composite Tanks for Storage of High Pressure Hydrogen

Comparison of Wall-Temperatures of Two Types of Large Capacity Cylinders for Tube Trailers During CNG Loading Processes

Comparisons of Testing Methods for High-Pressure Hydrogen Storage Container Under the Law and Regulation System of UN and EU

Engineering Application of Miniature Specimen Sampling Method on FFS Assessment of Corrosive Pits of In-Service Pressure Pipeline

Buckling Instability Analysis and Stiffeners Optimization Design for Large Vacuum Spherical Tanks

Application of Failure Mode and Effect Analysis on Centrifugal Pumps of Atmospheric and Vacuum Distillation Unit

Building the UK ABWR: Developments in Structural Integrity Safety Cases for Highest Reliability Components in the UK

Recent Studies Towards Updating the BS7910 Flaw Interaction Rule

NTD ASI, Section IV: Evaluation of Residual Lifetime of Components and Piping in WWER Type NPPs

RCC-M Code: Main Evolutions From the 2016 to 2018 Editions

Overview of Recent Activities Undertaken by the UK Forum for Engineering Structural Integrity (FESI)

Thermal Fatigue Evaluation Based on the Methods for Structural Stress Determination According to EN 13445-3 Annex NA: Comparison With Other Codes

UK Programme on Codes, Standard and Procedure Needs for SMR and Gen IV Reactors

Normative Technical Documentation of Association of Mechanical Engineers, Czech National Code of Equipment and Piping of Nuclear Power Plants of WWER Type

Effect of Chronological Order of Cyclic Loads With Different Amplitudes on Fatigue Crack Growth

Development of Crack Evaluation Models for Probabilistic Fracture Mechanics Analyses of Japanese Reactor Pressure Vessels

Sensitivity Study on the Effects of Nondestructive Examinations on Failure Probabilities of Reactor Pressure Vessels

Proposal of Flaw Evaluation Method for Securing Reliability of Circumferential Flawed Pipes

Crack Remaining Repair Techniques in Japan

Guideline on Application Process of Techniques Developed for Repair, Replacement and Mitigation Activities

Study on Promoting Use of Repair, Replacement and Mitigation Techniques in Maintenance Activities of Nuclear Power Plants

Temporary Acceptance of Leaking Brazed Joints

Code Case N-822 for Pin Brazing Non-Structural Attachment Tabs for Buried Pipe Cathodic Protection

Development of Improved Equations for Weld Heat Input and Dilution Control: Part 2

Formable Duplex Stainless Steel for High Pressure GPHE Applications

Factors Affecting the Oxidation and Carburisation Behaviour of an Austenitic Stainless Steel Used in the UK Advanced Gas-Cooled Reactors

Demonstrate ASME Section XI Appendix G Margins for Pressurized Water Reactor Inlet and Outlet Nozzle Corner Regions

Application of the FAVOR-OCI Fracture Mechanics Computer Program to ASME Code Section XI, IWB-3610 Flaw Acceptance Criteria Evaluations

A Comparative Study of Pressure Area Method of Nozzle Compensation in ASME Section VIII Division 2 and PD 5500 for Restrictions in Nozzle Dimensions

Investigations of Very High Cycle Fatigue Behavior of Metastable Austenitic Steels Using Servohydraulic and Ultrasonic Testing Systems

HRSG-Header Welds Residual-Stress Evaluation and Creep-Assessment Through the Application of Italian Code, American Standard

Proposed Review Framework for Design of Pressure Retaining Systems and Components (PRSC) in Small Modular Reactor (SMR)

Rapid Thermal Stress Ratcheting Assessment for Pressured Components Based on LMM

Verification of Probabilistic Fracture Mechanics Analysis Code Through Benchmark Analyses

Pilot Study for Uncertainty Analysis in Probabilistic Fitness-for-Service Evaluations of Zr-2.5Nb Pressure Tubes: Identification of Influential Variables

Pilot Study for Uncertainty Analysis in Probabilistic Fitness-for-Service Evaluations of Zr-2.5Nb Pressure Tubes: Uncertainty Characterization

The Reciprocal Effect Among a Quarter-Circle Corner Crack and a Non-Aligned Surface Crack of Comparable Size in an Infinitely Large Plate Under Uniaxial Tension

PTS on Embedded Rotated Cracks and Projection Rules

Tentative Thickness for Torispherical and Ellipsoidal ASME Section III Class 1 Heads

Volume 3B: Design and Analysis

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Volume 7: Operations, Applications, and Components

Volume 1A: Codes and Standards

Volume 6A: Materials and Fabrication

Volume 5: High-Pressure Technology; ASME Nondestructive Evaluation, Diagnosis and Prognosis Division (NDPD); Rudy Scavuzzo Student Paper Symposium and 26th Annual Student Paper Competition

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Management of Complex Loading Histories for Use in Probabilistic Creep-Fatigue Damage Assessments

Content Provider	The American Society of Mechanical Engineers (ASME) Digital Collection
Author	Zentuti, N. A. Booker, J. D. Bradford, R. A. W. Truman, C. E.
Copyright Year	2018
Abstract	An approach is outlined for the treatment of stresses in complex three-dimensional components for the purpose of conducting probabilistic creep-fatigue lifetime assessments. For conventional deterministic assessments, the stress state in a plant component is found using thermal and mechanical (elastic) finite element (FE) models. Key inputs are typically steam temperatures and pressures, with the three principal stress components (PSCs) at the assessment location(s) being the outputs. This paper presents an approach which was developed based on application experience with a tube-plate ligament (TPL) component, for which historical data was available. Though both transient as well as steady-state conditions can have large contributions towards the creep-fatigue damage, this work is mainly concerned with the latter. In a probabilistic assessment, the aim of this approach is to replace time intensive FE runs with a predictive model to approximate stresses at various assessment locations. This is achieved by firstly modelling a wide range of typical loading conditions using FE models to obtain the desire stresses. Based on the results from these FE runs, a probability map is produced and input(s)-output(s) functions are fitted (either using a Response Surface Method or Linear Regression). These models are thereafter used to predict stresses as functions of the input parameter(s) directly. This mitigates running an FE model for every probabilistic trial (of which there typically may be more than 104), an approach which would be computationally prohibitive.
Sponsorship	Pressure Vessels and Piping Division
File Format	PDF
ISBN	9780791851593
DOI	10.1115/PVP2018-84400
Volume Number	Volume 1B: Codes and Standards
Conference Proceedings	ASME 2018 Pressure Vessels and Piping Conference
Language	English
Publisher Date	2018-07-15
Publisher Place	Prague, Czech Republic
Access Restriction	Subscribed
Subject Keyword	Damage assessment Temperature Creep Probability Fatigue Response surface methodology Modeling Steady state Stress Transients (dynamics) Finite element model Steam Finite element analysis Damage
Content Type	Text
Resource Type	Article

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