Hostname: page-component-78c5997874-8bhkd Total loading time: 0 Render date: 2024-11-09T12:42:48.499Z Has data issue: false hasContentIssue false

The Effect of Fabrication Processes on the Governing Mechanical Failure Criteria for Alloy 22, Ti-Grade 2/7, and Ti-Grade 5/24 Alloys

Published online by Cambridge University Press:  17 March 2011

Aladar A. Csontos
Affiliation:
U.S. Nuclear Regulatory Commission, Mailstop: T7-F3, Washington, DC 20555-0001, USA
Darrell S. Dunn
Affiliation:
Center for Nuclear Waste Regulatory Analyses, Southwest Research Institute, 6220 Culebra Road, San Antonio, TX 78238-5166, USA
Yi-Ming Pan
Affiliation:
Center for Nuclear Waste Regulatory Analyses, Southwest Research Institute, 6220 Culebra Road, San Antonio, TX 78238-5166, USA
Gustavo A. Cragnolino
Affiliation:
Center for Nuclear Waste Regulatory Analyses, Southwest Research Institute, 6220 Culebra Road, San Antonio, TX 78238-5166, USA
Get access

Abstract

The effect of fabrication processes on the governing mechanical failure criteria for Alloy 22, Ti-Grade 2/7, and Ti-Grade 5/24 has been evaluated through the development of material specific failure assessment diagrams (FAD). The Barsom and Rolfe Charpy V-Notch (CVN) energy to KICempirical relationship was shown to be conservative when compared to experimental KJC data for Alloy 600 and 690, which indicates that the KIC derivation is most likely conservative for Alloy 22 as well. In contrast, the CVN to KICH2 relationship was found to be non-conservative for Ti-Grade 2/7 and Ti-Grade 5/24. The derived KIC value for Alloy 22 was then used to construct a K-based FAD, which indicated that the governing mechanical failure theory was the Tresca criterion for plastic collapse. Both the derived KIC and experimental KQ values were used in the development of the Ti-Grade 2/7 and Ti-Grade 5/24 FADs. The Ti-Grade 2/7 FAD indicated that the governing mechanical failure theory is also plastic collapse while the Ti-Grade 5/24 FADsuggested mixed mode failure processes where neither linear-elastic fracture mechanics (LEFM) nor Tresca can accurately predict.

Type
Research Article
Copyright
Copyright © Materials Research Society 2004

Access options

Get access to the full version of this content by using one of the access options below. (Log in options will check for institutional or personal access. Content may require purchase if you do not have access.)

References

1. Dowling, A.R. and Townley, C.H., “The Effects of Defects on Structural Failure: A Two-Criteria Approach,” Intrnl. Journal of Pressure Vessels and Piping,Vol. 3,p. 77137, 1975 Google Scholar
2. Harrison, R.P., Loosemore, K., and Milne, I., “Assessment of the Integrity of Structures Containing Defects,” CEGB Report R/H/R6, Central Electricity Generating Board, UK, 1976.Google Scholar
3. Anderson, T.L., “Fracture Mechanics: Fundamentals and Applications”, 2nd Edition, CRC Press, Boca Raton, FL, TIC: 246278, 1995.Google Scholar
4.Bechtel SAIC Company, LLC, “Comparison of the Traditional Strength of Materials Approach to Design with the Fracture Mechanics Approach,” CAL-EBS-ME-000019 REV 00, ACC: MOL 20020508.0274, 2002.Google Scholar
5. Rolfe, S.T. and Novak, S.R., Slow Bend KIC Testing of Medium Strength High Toughness Steels,” ASTM STP 463, American Soc. of Testing and Mat., Philadelphia, p. 124–159, 1970.Google Scholar
6. Barsom, J.M. and Rolfe, S.T., “Correlation Between KIC and Charpy V Notch Test Results in the Transition Temperature Range,” ASTM STP 466, American Soc. of Testing and Mat., Philadelphia, p. 281–302, 1970.Google Scholar
7. Materials Properties Handbook: Titanium Alloys, eds. Boyer, R., Welsch, G., and Collings, E.W., ASM International, Materials Park, OH, ISBN 0-87170-481-1, 1994.Google Scholar
8. Mills, W.J. and Brown, C.M., “Fracture Behavior of Ni-Based Alloys inWater”, 9th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, Edited by Ford, F.P., et. al, TMS, 1999.Google Scholar
9. Mills, W.J. and Brown, C.M., "Fracture Toughness of Alloy 600 and an EN82H Weld in Air & Water", Met. And Mat. Trans. A, Vol. 32A, May 2001.Google Scholar
10. Summers, T.S.E., Rebak, R.B., Palmer, T.A., and Crook, P., “Influence of Thermal Aging on the Mechanical and Corrosion Properties of GTAW Welds on All N06022,” Scientific Basis for Nuclear Waste Management XXV, Symposium Proceedings 713,eds. McGrail, G.P. and Cragnolino, G.A., Warrendale, , PA, Materials Research Society, pp. 45-52, 2002.Google Scholar
11. Andresen, P.L., Young, L.M., Catlin, G.M., and Emigh, P.W., 2003 TMS Fall Meeting – Effect of Processing on Materials Properties for Nuclear Waste Disposition Conference Proceedings, Met. Trans., ed. Rebak, R., in press, 2004.Google Scholar