On the assessment of through-wall circumferential cracks in steam generator tubes with tube supports

Journal of Pressure Vessel Technology, Transactions of the ASME

Volumn 125, Issue 1, 2003, Pages 85-90

  Wang, Xin ^a   Reinhardt, Wolf ^b  

^a CARLETON UNIVERSITY   (Canada)

^b Nuclear Engineering   (Canada)

Author keywords

[No Author keywords available]

Indexed keywords

CRACKS; FAILURE ANALYSIS; STRESS INTENSITY FACTORS; TUBES (COMPONENTS);

FAILURE ASSESSMENT DIAGRAM (FAD);

STEAM GENERATORS;

EID: 0037328452     PISSN: 00949930     EISSN: None     Source Type: Journal    
DOI: 10.1115/1.1511737     Document Type: Article

References (11)

1. NRC Regulatory Guide 1.121, 1976, "Bases for Plugging Degraded PWD Steam Generator Tubes," U.S. Nuclear Regulatory Commission, Aug.
2. ASME Boiler & Pressure Vessel Code, 1998 Edition, Section III and XI, including Appendices.
3. Bloom, J., 1985, "Deformation Plasticity Failure Assessment Diagram," Elastic-Plastic Fracture Mechanics Technology, ASTM Spec. Tech. Publ., ASTM STP 896.
4. EPRI TR-107197-P1 & P2, Interim Report, 1997, "Depth-Based Structural Analysis Methods for Steam Generator Circumferential Indications," Nov.
5. I Solutions for Single Edge Notch Specimens under Fixed End Displacement," Int. J. Fract., 31, pp. 53-65.
6. Anderson, T. L., 1995, Fracture Mechanics, Fundamentals and Applications, Second Edition, CRC Press Inc., Boca Raton, FL.
7. Mathcad 6.0, 1995, User's Manual, MatSoft Inc.
8. Huntington Alloys, 1980, "Inconel Alloy 690," Huntington Alloys, Inc.
9. th Edition, ANSYS Inc.
10. PD 6493:1991, 1991, "Guidance on Some Methods for the Derivation of Acceptance Levels for Defects in Fusion Welded Joints," British Standards Institution, Aug.
11. Young, W. C., 1989, Roark's Formulas for Stress and Strain, 6th Edition, McGraw-Hill Inc., New York. NY.