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.

1.
Rudland
,
D. L.
,
Shim
,
D. -J.
,
Xu
,
H.
, and
Wilkowski
,
G. W.
, 2007, “
Evaluation of Circumferential Indications in Pressurizer Nozzle Dissimilar Metal Welds at the Wolf Creek Power Plant
,” NRC Summary Report No. ADAMS ML071560398.
2.
2007, “
Advanced FEA Evaluation of Growth of Postulated Circumferential PWSCC Flaws in Pressurizer Nozzle Dissimilar Metal Welds (MRP-216, Rev. 1)
,” EPRI Report No. 1015383.
3.
Rudland
,
D. L.
,
Shim
,
D. -J.
,
Zhang
,
T.
, and
Wilkowski
,
G.
, 2007, “
Implications of Wolf Creek Indications—Final Report
,” NRC Program Final Report No. ADAMS ML072470394.
4.
ABAQUS, Inc.
, 2006, ABAQUS Version, 6.6–1 User’s Manual.
5.
Quest Reliability
, 2008, FEACrack, 3D Finite Element Software for Cracks, Version 3.0 Users Manual.
6.
Anderson
,
T. L.
,
Thornwald
,
G.
,
Revelle
,
D. A.
, and
Lanaud
,
C.
, 2000, “
Stress Intensity Solutions for Surface Cracks and Buried Cracks in Cylinders, Spheres, and Flat Plates
,” Structural Reliability Technology Final Report to the Materials Property Council.
7.
Rudland
,
D.
,
Xu
,
H.
,
Wilkowski
,
G.
,
Scott
,
P.
,
Ghadiali
,
N.
, and
Brust
,
F.
, 2006, “
Development of a New Generation Computer Code (PRO-LOCA) for the Prediction of Break Probabilities for Commercial Nuclear Power Plants Loss-Of-Coolant Accidents
,”
Proceedings of ASME-PVP 2006 ASME Pressure Vessels and Piping Division Conference
, July 23–27, Vancouver, BC, Canada.
8.
Rudland
,
D.
,
Scott
,
P.
,
Kurth
,
R.
, and
Cox
,
A.
, 2009, “
Continuing Development of PRO-LOCA for the Prediction of Break Probabilities for Loss-Of-Coolant Accidents
,”
Proceedings of ASME-PVP 2009 ASME Pressure Vessels and Piping Division Conference
, July 26–30, Prague, Czech Republic.
9.
White
,
G. A.
,
Nordmann
,
N. S.
,
Hinkling
,
J.
, and
Harrington
,
C. D.
, 2005, “
Development of Crack Growth Rate Disposition Curves for Primary Water Stress Corrosion Cracking (PWSCC) of Alloy 82, 182 and 132 Weldments
,”
Proceedings of the 12th International Conference on Environmental Degradation of Nuclear Power Systems—Water Reactors
,
The Minerals, Metals and Materials Society
,
Salt Lake City, UT
.
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