NDLI: Crack Growth Under Thermal Fatigue Loading (Effect of Stress Gradient and Relaxation)

Content Provider	The American Society of Mechanical Engineers (ASME) Digital Collection
Author	Kamaya, Masayuki
Copyright Year	2009
Abstract	Thermal fatigue is a critical problem in nuclear power plants. To prevent crack initiation, JSME has issued a guideline for design. In this study, the feasibility of incorporating crack growth analysis into the design and integrity evaluation was investigated. Two characteristics of thermal fatigue loading were considered. The first was the effects of stress gradient in the depth direction. It was shown that the steep stress gradient near the surface significantly reduced the stress intensity factor (SIF) of deep cracks. Assuming that crack growth is arrested by small SIF, it is possible to leave detected cracks unrepaired. Otherwise, the cracks should be removed regardless of their size. The other characteristic is the displacement controlled boundary condition. Through finite element analyses, it was revealed that the displacement controlled boundary condition reduces SIF, and the magnitude of the reduction in SIF depends on the crack depth and boundary length. It is concluded that, under thermal fatigue loading, the cracks that are detected in the in-service inspection have already been arrested if they do not penetrate the wall thickness. The crack arrest scenario is a reasonable method of assessing the integrity of cracked components.
Sponsorship	Pressure Vessels and Piping
Starting Page	433
Ending Page	440
Page Count	8
File Format	PDF
ISBN	9780791843666
DOI	10.1115/PVP2009-77547
e-ISBN	9780791838549
Volume Number	Volume 3: Design and Analysis
Conference Proceedings	ASME 2009 Pressure Vessels and Piping Conference
Language	English
Publisher Date	2009-07-26
Publisher Place	Prague, Czech Republic
Access Restriction	Subscribed
Subject Keyword	Design Relaxation (physics) Japan society of mechanical engineers Fatigue Boundary-value problems Fracture (materials) Finite element analysis In-service inspection Nuclear power stations Wall thickness Stress Displacement
Content Type	Text
Resource Type	Article

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