Limit Loads for Circumferential Cracks in the Steam Generator Tube under Combined Pressure and Bending Loads


Article Preview

Steam generator in a nuclear power plant is huge heat exchanger that transfers heat from reactor to make steam to drive turbine-generator. Failure of the steam generator tubes can result in the release of fission products to the secondary side. Therefore, accurate integrity assessment of the cracked steam generator tubes is of great importance for maintaining the safety of the nuclear power plant. This paper provides limit loads for circumferential through-wall cracks in steam generator tubes under combined internal pressure and bending loads. Such limit loads are developed on the basis of three dimensional finite element analyses assuming elastic-perfectly plastic material behavior. As for the crack location, both the top of the tubesheet and U-bend regions are considered. The analysis results can be directly applied to the practical integrity assessment of cracked steam generator tubes, because the comparison between experimental data and FE results shows a very good agreement.



Key Engineering Materials (Volumes 345-346)

Edited by:

S.W. Nam, Y.W. Chang, S.B. Lee and N.J. Kim




H. S. Kim et al., "Limit Loads for Circumferential Cracks in the Steam Generator Tube under Combined Pressure and Bending Loads ", Key Engineering Materials, Vols. 345-346, pp. 1357-1360, 2007

Online since:

August 2007




[1] R. Keating and J. Begley: Steam Generator Degradation Specific Management Flaw Handbook, 1001191 (EPRI, U.S. 2001).

[2] A. Zahoor: Ductile Fracture Handbook, NP-6301-D (EPRI, U.S. 1989).

[3] M.F. Kanninen, et al.: Mechanical Fracture Predictions for Sensitized Stainless Steel Piping with Circumferential Cracks, NP-192, (EPRI, U.S. 1976).

[4] A.G. Miller: International Journal of Pressure Vessels and Piping Vol. 32 (1988), p.197~327.

[5] S. Majumdar, K. Kasza and J. Franklin: Pressures and Leak-Rate Tests and Models for Predicting Failure of Flawed Steam Generator Tubes, NUREG/CR-6664 (USNRC, U.S. 2000).

[6] H.S. Kim, J.S. Kim, T.E. Jin, H.D. Kim and H.S. Chung: Key Engineering Materials Vol. 270~273 (2004), p.1240~1245.

[7] HKS: ABAQUS Ver. 6. 5-1 User's Manual (HKS Inc., U.S. 2005).

[8] R.C. Cipolla, et al.: Impacts of the Structural Integrity Performance Criterion on Steam Generator Tube Integrity Evaluation, 1009541 (EPRI, U.S. 2004).