Skip to main content
Log in

Effect of welding parameters on fracture resistance characteristics of nuclear piping

  • Published:
International Journal of Precision Engineering and Manufacturing Aims and scope Submit manuscript

Abstract

To guarantee the safety of nuclear power plants during operation and maintain coolant pipe integrity during life time, the evaluation of the coolant pipe integrity is necessary. The welded part is the most vulnerable place for the crack initiation and subsequent growth. Moreover, the weld width and the crack location also affected the deformation and fracture behavior of the welded part. Therefore, the evaluation of the welded part integrity in the coolant pipe while considering the residual stresses and welding defects is very important. In recent years, FE analysis about the welded parts in a pipe has been performed to evaluate the fracture toughness characteristics for the welded parts with various welding parameters. However, test method has not been proposed to evaluate the fracture toughness properties of the welded parts in a pipe. In this study, piping materials which are equivalent to those in safety injection pipes of nuclear power plants were welded to form a butt welding part. Then, fracture toughness tests for base metal, the similar and the dissimilar welded parts were performed to evaluate the effect of welding parameters.

This is a preview of subscription content, log in via an institution to check access.

Access this article

Price excludes VAT (USA)
Tax calculation will be finalised during checkout.

Instant access to the full article PDF.

Similar content being viewed by others

Abbreviations

α :

Coefficient of Ramberg-Osgood model

n :

Strain hardening exponent of Ramberg-Osgood model

σ :

Stress

ε :

Strain

σ 0 :

Yield strength as a reference

ε 0 :

Yield strain as a reference

References

  1. Huh, N. S., Shim, D. J., Kim, Y. J., and Kim, Y. J., “Reference Stress based Fracture Mechanics Analysis for Circumferential Through-Wall Cracked Pipes — Comparison with Pipe Test Data,” Proc. of KSME Conference, pp. 389–395, 2003.

    Google Scholar 

  2. Han, T. S., Huh, N. S., and Park, C. Y., “Evaluation of Crack Growth Estimation Parameters of Thick-Walled Cylinder with Non-Idealized Circumferential Through-Wall Cracks,” Journal of the Korean Society for Nondestructive Testing, Vol. 33, No. 2, pp. 138–146, 2013.

    Article  Google Scholar 

  3. Yi, H. B., Lee, J., and Kang, T., “A Seismic Stability Design by the KEPIC Code of Main Pipe in Reactor Containment Building of a Nuclear Power Plant,” J. Korean Soc. Precis. Eng., Vol. 28, No. 2, pp. 233–238, 2011.

    Google Scholar 

  4. Li, S., Zhang, H., Li, S., Wang, Y., Xue, F., and Wang, X., “Probabilistic Fracture Mechanics Analysis of Thermally Aged Nuclear Piping in a Pressurized Water Reactor,” Nuclear Engineering and Design, Vol. 265, pp. 611–618, 2013.

    Article  Google Scholar 

  5. Saxena, S. and Ramachandra Murthy, D., “On the Accuracy of Ductile Fracture Assessment of Through-Wall Cracked Pipes,” Engineering Structures, Vol. 29, No. 5, pp. 789–801, 2007.

    Article  Google Scholar 

  6. Chiodo, M. S., and Ruggieri, C., “J and CTOD Estimation Procedure for Circumferential Surface Cracks in Pipes under Bending,” Engineering Fracture Mechanics, Vol. 77, No. 3, pp. 415–436, 2010.

    Article  Google Scholar 

  7. ASME, “BPVC Section XI-Rules for Inservice Inspection of Nuclear Power Plant Components,” 2013.

    Google Scholar 

  8. ASTM, “Standard Test Method for Measurement of Fracture Toughness,” Document ID: E1820, 2001.

    Google Scholar 

  9. ASTM, “Standard Test Methods for Tension Testing of Metallic Materials,” Document ID: E8/E8M, 2013.

    Google Scholar 

  10. Castelluccio, G. M., Perez Ipiña, J. E., Yawny, A. A., and Ernst, H. A., “Fracture Testing of the Heat Affected Zone from Welded Steel Pipes using an in Situ Stage,” Engineering Fracture Mechanics, Vol. 98, pp. 52–63, 2013.

    Article  Google Scholar 

  11. Kim, Y. J. and Schwalbe, K. H., “Mismatch Effect on Plastic Yield Loads in Idealized Weldments-I: Weld Centre Cracks,” Engineering Fracture Mechanics, Vol. 68, pp. 163–182, 2001.

    Article  Google Scholar 

  12. Kim, Y. J. and Schwalbe, K. H., “Mismatch Effect on Plastic Yield Loads in Idealized Weldments-II: Heat Affected Zone Cracks,” Engineering Fracture Mechanics, Vol. 68, pp. 183–199, 2001.

    Article  Google Scholar 

  13. Rahman, S., “Probabilistic Elastic-Plastic Fracture Analysis of Circumferentially Cracked Pipes with Finite-Length Surface Flaws,” Nuclear Engineering and Design, Vol. 195, No. 3, pp. 239–260, 2000.

    Article  Google Scholar 

  14. Saxena, S. and Ramachandra Murthy, D., “Elastic-Plastic Fracture Mechanics based Prediction of Crack Initiation Load in Through-Wall Cracked Pipes,” Engineering Structures, Vol. 26, No. 9, pp. 1165–1172, 2004.

    Article  Google Scholar 

  15. Bouchard, P., “Validated Residual Stress Profiles for Fracture Assessments of Stainless Steel Pipe Girth Welds,” International Journal of Pressure Vessels and Piping, Vol. 84, No. 4, pp. 195–222, 2007.

    Article  MathSciNet  Google Scholar 

  16. Wang, H. T., Wang, G. Z., Xuan, F. Z., and Tu, S. T., “Fracture Mechanism of a Dissimilar Metal Welded Joint in Nuclear Power Plant,” Engineering Failure Analysis, Vol. 28, pp. 134–148, 2013.

    Article  Google Scholar 

  17. Kim, J. Y., Cho, G. J., and Kim, C. H., “Ultrasonic Signal Analysis with DSP for the Pattern Recognition of Welding Flaws,” Int. J. Precis. Eng. Manuf., Vol. 1, No. 1, pp. 106–110, 2000.

    Google Scholar 

  18. Kim, Y. J., Kim, J. S., Cho, S. M., and Kim, Y. J., “3-D Constraint Effects on J Testing and Crack Tip Constraint in M(T), SE(B), SE (T) and C(T) Specimens: Numerical Study,” Engineering Fracture Mechanics, Vol. 71, No. 9, pp. 1203–1218, 2004.

    Article  Google Scholar 

  19. Park, J. S., Seok, C. S., and Kim, Y. J., “A Study on the Evaluation of the Pipe Fracture Characteristic,” Trans. Korean Soc. Mech. Eng., Vol. 29, No. 1, pp. 107–114, 2005.

    Article  Google Scholar 

Download references

Author information

Authors and Affiliations

Authors

Corresponding author

Correspondence to Chang-Sung Seok.

Rights and permissions

Reprints and permissions

About this article

Check for updates. Verify currency and authenticity via CrossMark

Cite this article

Shin, IH., Park, SK., Kim, SY. et al. Effect of welding parameters on fracture resistance characteristics of nuclear piping. Int. J. Precis. Eng. Manuf. 16, 65–71 (2015). https://doi.org/10.1007/s12541-015-0008-2

Download citation

  • Received:

  • Revised:

  • Accepted:

  • Published:

  • Issue Date:

  • DOI: https://doi.org/10.1007/s12541-015-0008-2

Keywords

Navigation