Failure assessment diagrams for high temperature defect assessment

Engineering Fracture Mechanics

Volumn 62, Issue 1, 1999, Pages 95-109

  Ainsworth, R A ^a   Hooton, D G ^b   Green, D ^b  

^a Nuclear Electric Ltd   (United Kingdom)

^b RICARDO UK LTD   (United Kingdom)

Author keywords

Crack growth; Creep; Creep fatigue; Failure assessment diagram

Indexed keywords

CRACK PROPAGATION; CREEP; FAILURE ANALYSIS; FATIGUE OF MATERIALS; HIGH TEMPERATURE EFFECTS;

CREEP-FATIGUE; FAILURE ASSESSMENT DIAGRAM (FAD) METHODS;

FRACTURE MECHANICS;

EID: 0032639774     PISSN: 00137944     EISSN: None     Source Type: Journal    
DOI: 10.1016/s0013-7944(98)00087-3     Document Type: Article

References (20)

1. R6, Assessment of the integrity of structures containing defects, Procedure R6, Revision 3. Gloucester, UK: Nuclear Electric Ltd, 1997.
2. Ainsworth RA, Budden PJ. Recent developments in the R6 failure assessment diagram approach to fracture assessment. In: Proceedings of the Institute of Materials 2nd Griffiths Conference, Sheffield, 1995:173-86.
3. Ainsworth RA. Flaw assessment methods using failure assessment diagrams. In: Proceedings of ECF 10, Berlin, vol. I. EMAS, Warley, 1994:121.
4. Ainsworth R.A. The use of a failure assessment diagram for initiation and propagation of defects at high temperatures. Fatigue Fract Engng Mater Struct. 16:1993;1091-1108.
5. Hooton DG, Green D, Ainsworth RA. An R6 type approach for the assessment of creep crack growth initiation in 316L stainless steel test specimens. In: ASME PVP Conference, Minneapolis, 1994;287:129-36.
6. Ainsworth RA, Hooton DG, Green D. Further developments of an R6 approach for the assessment of creep crack incubation. In: ASME PVP Conference, Honolulu, 1995;315:39-44.
7. R5, Assessment procedure for the high temperature response of structures, Procedure R5, Issue 2. Gloucester, UK: Nuclear Electric Ltd, 1997.
8. Webster GA, Ainsworth RA. High temperature component life assessment. London: Chapman and Hall, 1994.
9. Piques R., Bensussen P., Pineau A. Crack initiation and growth under creep fatigue loading of an austenitic stainless steel. Nuclear Engng Design. 116:1989;293-306.
10. ESIS. Procedure for determining the fracture behaviour of materials, ESIS P2-92. University of Technology, Delft, 1992.
11. ASME. Case of ASME boiler and pressure vessel code, section III - class I components in elevated temperature service. Code Case N47-29. New York: ASME, 1990.
12. AFCEN. Design and construction rules for mechanical components of FBR nuclear island. RCC-MR. Paris: AFCEN, 1985.
13. British Standards Institution. Guide to methods for the assessment of the influence of crack growth on the significance of defects in components operating at high temperatures. BS PD6539:1994, 1994.
14. American Society Testing Materials. Standard test method for measurement of creep crack growth rates in metals. ASTM E1457-92, 1992.
15. Ainsworth RA, Booth SE. Tearing-creep interaction. Nuclear Electric Report EPD/GEN/REP/0259/97, Gloucester, UK, 1997.
16. Curbishley I. The use of uniaxial creep data to predict creep crack growth behaviour in austenitic stainless steel. In: ESIS 15. London: MEP, 1993:441-51.
17. Gooch D.J., Kimmins S.T. C* correlations for creep crack growth in weld metals. J Strain Analysis. 21:1986;231-242.
18. Ainsworth R.A., Coleman M.C. Example of an application of an assessment procedure for defects in plant operating in the creep range. Fatigue Fract Engng Mater Struct. 10:1987;129-140.
19. Neate G.J. Creep crack growth in 1/2CrMoV steel at 838 K, I: behaviour at a constant load. Mater Sci Engng. 82:1986;59-76.
20. Coleman MC. Examination of fracture in a pressure vessel under creep conditions. In: Strauss BM, Cullen WH, Jr., editors. Fractography in failure analysis. ASTM STP 645, 1978:297-311.