Safety and structural integrity 2006 / edited by Young-Jin Kim.

Format:

Book

Conference/Event

Author/Creator:

International Symposium on Safety and Structural Integrity, Corporate Author.

Contributor:

Kim, Young-Jin, 1950- editor of compilation.

Conference Name:

International Symposium on Safety and Structural Integrity (2005 : Cheju-do, Korea), issuing body.

International Symposium on Safety and Structural Integrity

Series:

Diffusion and defect data. Solid state phenomena ; Pt. B, volume 120.

Diffusion and defect data. Pt. B, Solid state phenomena, 1012-0394 ; volume 120

Language:

English

Subjects (All):

Structural analysis (Engineering)--Congresses.

Structural analysis (Engineering).

Structural engineering--Research--Congresses.

Structural engineering.

Structural stability--Congresses.

Structural stability.

Physical Description:

1 online resource (286 p.)

Place of Publication:

Switzerland : Trans Tech Publications Ltd., [2007]

Language Note:

English

Summary:

The primary objective of this collection of 42 peer-reviewed authoritative articles is to share with the reader the very latest information on cutting-edge technologies in the fields of safety and structural integrity. The topics addressed by this collection span a wide range of issues: including fracture and fatigue cracking, reliability evaluation, NDE, modeling and design. Particular attention is paid to emerging techniques for the treatment of complicated structures.

Contents:

Safety and Structural Integrity 2006; Preface; Table of Contents; Corrosion and Corrosion Fatigue Characteristics of CF8A Steel Degraded for 3 Months at 400°C; Fatigue Life Evaluation of an Actual Structure under the Irregular Loading Using an Acceleration Test; A Study on the Estimation of Fracture Behaviour for a Circumferentially Through-Wall Cracked Pipe; Effect of Loading Frequency on Fatigue Crack Growth Behaviour and Microstructural Damage in P92 HAZ; Development of Web-Based Fatigue Life Evaluation System for Reactor Pressure Vessel

Socket Weld Integrity in Nuclear Piping under Fatigue Loading ConditionFailure Probability Estimation of Pressure Tube Using Failure Assessment Diagram; Evaluation of the Cleavage Fracture Toughness of RPV Steels Using Small Bend Specimens; Recent Japanese Probabilistic Fracture Mechanics Researches Related to Failure Probability of Aged RPV; Assessment of Steam Generator Tubes with Dual Axial Through-Wall Cracks; Allowable Subsurface Flaws Located Near Vessel Surface in JSME Code; Ductile Fracture Behaviour of Class 2 and 3 LWR Piping and Its Implications for Flaw Evaluation Criteria

Cracking Behaviours of Thermal ComponentsThe Study of Fatigue Crack Growth of 304SS with the Influence of Loading Frequency and Temperature; Enhancement of Flaw Detectability Using Time Reversal Techniques; Economic Evaluation of Maintenance Strategies for Steam Generator Tubes Using Probabilistic Fracture Mechanics and a Financial Method; An Efficient General Purpose Contact Search Algorithm Using the Relative Coordinate System for Multibody System Dynamics; Studies on a High-Temperature Air Combustion Burner for a Compact Fuel-Cell Reformer

Analysis of Thermal Stress and Flow Characteristics in a Bellows-Seal Valve for the Reliability EstablishmentFinite Element Alternating Method for Interacting Surface Cracks; Development of an Integrity Evaluation System for Steam Generator Tubes in a Nuclear Power Plant; Friction and Wear of POE and PAG Oils in the Carbon Dioxide Environment; Fault Detection for the Reliability of the Refrigerant Inventory of the System Air Conditioner; Enhanced Reliability of Mold Close and Open Control in Injection Molding Machine through Fuzzy Algorithm

Wear Characteristics of Tube-Support Components for a Nuclear Steam Generator under Fretting ConditionsAnalysis of Burst Pressure of Damaged Tubes Using Plastic Instability Analysis; Aging Management of Nuclear Power Plants in Korea; Proposal of Rationalized Assessment Procedure for Buckling of Thin-Walled Cylindrical Tanks; The Sliding and Overturning Analysis of a Free-Standing Cask under Earthquake; The Application of Risk-Informed-Inservice Inspection to Recirculation Piping Welds of a Nuclear Power Plant

Advanced Active Safety System Using Separated Front and Rear Motor Control for a 4WD Hybrid Electric Vehicle

Notes:

Description based upon print version of record.

Includes bibliographical references and indexes.

Description based on print version record.

ISBN:

3-03813-137-7

1-61344-730-2