Typical ASME Section XI subcritical cracking analyses assume an idealized flaw shape driven by stress intensity factors developed for semi-elliptical shaped flaws. Recent advanced finite element analyses (AFEA) conducted by both the United States Nuclear Regulatory Commission (U.S.NRC) and the nuclear industry for long circumferential indications found in the pressurizer nozzle dissimilar metal welds at the Wolf Creek power plant suggest that the semi-elliptical flaw assumption may be overly conservative in some cases. The AFEA methodology that was developed allowed the progression of a planar flaw subjected to typical stress corrosion cracking (SCC)-type growth laws by calculating stress intensity factors at every nodal point along the crack front, and incrementally advancing the crack front in a more natural manner. Typically, crack growth analyses increment the semi-elliptical flaw by considering only the stress intensity factor at the deepest and surface locations along the crack front, while keeping the flaw shape semi-elliptical. In this paper, a brief background to the AFEA methodology and the analyses conducted in the Wolf Creek effort will be discussed. In addition, the predicted behavior of surface cracks under normal operating conditions (plus welding residual stress) using AFEA will be investigated and compared with the semi-elliptical assumption. Conclusions on the observation of when semi-elliptical flaw assumptions are appropriate will be made. These observations will add insight into the conservatism of using an idealized flaw shape assumption.
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February 2010
Research Papers
Stress Corrosion Crack Shape Development Using AFEA
D. Rudland,
D. Rudland
Office of Nuclear Regulatory Research,
e-mail: david.rudland@nrc.gov
U.S. Nuclear Regulatory Commission
, Mail Stop: C-05C04, Washington, DC 20555-0001
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A. Csontos,
A. Csontos
Office of Nuclear Regulatory Research,
U.S. Nuclear Regulatory Commission
, Mail Stop: C-05C04, Washington, DC 20555-0001
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D.-J. Shim
D.-J. Shim
Engineering Mechanics Corporation of Columbus
, 3518 Riverside Drive, Suite 202, Columbus, OH 43221
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D. Rudland
Office of Nuclear Regulatory Research,
U.S. Nuclear Regulatory Commission
, Mail Stop: C-05C04, Washington, DC 20555-0001e-mail: david.rudland@nrc.gov
A. Csontos
Office of Nuclear Regulatory Research,
U.S. Nuclear Regulatory Commission
, Mail Stop: C-05C04, Washington, DC 20555-0001
D.-J. Shim
Engineering Mechanics Corporation of Columbus
, 3518 Riverside Drive, Suite 202, Columbus, OH 43221J. Pressure Vessel Technol. Feb 2010, 132(1): 011406 (7 pages)
Published Online: January 5, 2010
Article history
Received:
November 19, 2008
Revised:
May 28, 2009
Online:
January 5, 2010
Published:
January 5, 2010
Citation
Rudland, D., Csontos, A., and Shim, D. (January 5, 2010). "Stress Corrosion Crack Shape Development Using AFEA." ASME. J. Pressure Vessel Technol. February 2010; 132(1): 011406. https://doi.org/10.1115/1.4000349
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