DOI QR코드

DOI QR Code

Effect of Preemptive Weld Overlay on Residual Stress Mitigation for Dissimilar Metal Weld of Nuclear Power Plant Pressurizer

예방 용접 Overlay가 원전 가압기 이종금속용접부 잔류응력 완화에 미치는 영향

  • 송태광 (고려대학교 대학원 기계공학과) ;
  • 배홍열 (고려대학교 대학원 기계공학과) ;
  • 전윤배 (고려대학교 대학원 기계공학과) ;
  • 오창영 (고려대학교 대학원 기계공학과) ;
  • 김윤재 (고려대학교 기계공학과) ;
  • 이경수 (한전 전력연구원) ;
  • 박치용 (한전 전력연구원)
  • Published : 2008.10.01

Abstract

Weld overlay is one of the residual stress mitigation methods which arrest crack initiation and crack growth. Therefore weld overlay can be applied to the region where cracking is likely to be. An overlay weld used in this manner is termed a preemptive weld overlay(PWOL). In pressurized water reactor(PWR) dissimilar metal weld is susceptible region for primary water stress corrosion cracking(PWSCC). In order to examine the effect of PWOL on residual stress mitigation, PWOL was applied to a specific dissimilar metal weld of Kori nuclear power plant by finite element analysis method. As a result, strong compressive residual stress was made in PWSCC susceptible region and PWOL was proved effective preemptive repair method for weldment.

Keywords

References

  1. Material Reliability Program : Welding Residual and Operating Stresses in PWR Alloy 182 Butt Welds (MRP-106), EPRI, Palo Alto, CA:2004. 1009378
  2. Bamford, W., Newton, B. and Seeger, D., 2006, "Recent Experience with Weld Overlay Repair of Indications in Alloy 182 Butt Welds in Two Operating PWRs," Trans. of ASME PVP conference, PVP2006-ICPVT-11-93891
  3. Tsuruta, T., Sato, K., Asada, S., Kobayashi, T., Okimura, K. and Matsubara, N., 2008, "PWSCC of Nickel Base Alloys in Vapor Phase Environment of Pressurizer," Proceedings of the $16^{th}$ international conference on nuclear engineering, ICONE16-48377
  4. Fox, M., 1979, "An Overview of Intergranular Corrosion Cracking in BWRs," Journal of Materials in energy system, 1:3
  5. Okimura, K., Konno, T., Narita, M., Ohta, T. and Toyoda, M., 2008, Reliability of Water Jet Peening as Residual Stress Improvement Method for Alloy 600 PWSCC Mitigation," Proceedings of the $16^{th}$ international conference on nuclear engineering, ICONE16-48375
  6. British Energy Generation Ltd., 2004, Asessment of the Intergrity of Structures Containing Defects, R6, II.7
  7. Smith, D. J. and Garwood, S. J., 1992, "Influence of Postweld Heat Treatment on the Variation of Residual Stresses in 50 mm Thick Welded Ferritic Steel Plates," Int. J. Pres. Ves. & Piping, Vol. 51, pp. 241-256 https://doi.org/10.1016/0308-0161(92)90083-R
  8. ASME, 2004, Welding and Brazing Qualification, ASME Boiler and Pressure Vessel Code, Sec. IX
  9. ASME, 2004, Rule for Construction of Nuclear Power Plant Components, ASME Boiler and Pressure Vessel Code, Sec. III
  10. Hamada, I. and Yamauchi, K., 2002, "Sensitization Behavior of Type 308 Stainless Steel Weld Metals After Postweld Heat Treatment and Low-emperature Aging and Its Relation to Microstructure," Metallurgical and Materials Transactions A, Vol. 33A, pp. 1743-1754 https://doi.org/10.1007/s11661-002-0183-5
  11. Abel, J.S, Titrington, J., Jordan, R., Porowski, J. S., O'Donnell, W. J., Badlani, M. L. and Hampton, E. J., 1988, "Mechanical Methods of Improving Resistance to Stress Corrosion Cracking in BWR Piping Systems," Int. J. Pres. Ves. and piping, Vol. 34, pp. 17-29 https://doi.org/10.1016/0308-0161(88)90039-7
  12. Shimizu, T., Enomoto, K. and Sakata, S., 1984, "Residual Stresses in Girth Butt Welded Pipes and Treatments to Modify These," Int. J. Pres. Ves. & Piping, Vol. 16, pp. 299-319 https://doi.org/10.1016/0308-0161(84)90020-6
  13. Yen, H. J., Lin, M. C. and Chen, L. J., 1996, "Residual Stress Measurement in 304 Stainless Steel Weld Overlay Pipes," J. of Engineering Materials and Technology, Vol. 118, pp. 135-142 https://doi.org/10.1115/1.2805927
  14. Porouski, J. S., O'Donnell, W. J., Bandlani, M. L., Hampton, E. J. and Kasraie, B., 1992, "New Mechanical and Thermal Processes for Mitigating Stress - Corrosion and Corrosion-Accelerated Fatigue," Int. J. Pres. Ves. & Piping, Vol. 50, pp. 63-79 https://doi.org/10.1016/0308-0161(92)90030-J
  15. Hurrel, P. R., Everett, D., Gregg, A. and Bate, S., 2006, "Review of Residual Stress Mitigation Methods for Application in Nuclear Plant," Trans. of ASME PVP conference, PVP2006-ICPVT-11-93381
  16. Edwards, N. W., 1986, "Weld Overlay of BWR Flawed Piping," Int. J. Pres. Ves. & Piping, Vol 25, pp. 17-24 https://doi.org/10.1016/0308-0161(86)90090-6
  17. Riccardella, P. C., Pitcairn, D. R., Giannuzzi, A. J. and Gerber, T. L., 1988, "Weld Overlay Repairs from Conception to Long-Term Qualification," Int. J. Pres. Ves. & Piping, Vol. 34, pp. 59-82 https://doi.org/10.1016/0308-0161(88)90042-7
  18. Song, T. K., Bae, H. Y., Chun, Y. B., Oh, C. Y., Kim, Y. J., Lee, K. S. and Park, C. Y., 2008, "Estimation of Residual Stress Distribution for Pressurizer Nozzle of Kori Nuclear Power Plant Considering Safe End," Trans. of the KSME(A), Vol. 32, No. 8 https://doi.org/10.3795/KSME-A.2008.32.8.668
  19. Materials Reliability Program : Technical Basis for Preemptive Weld Overlays for Alloy 82/182 Butt Welds in PWRs (MRP-169), EPRI, Palo Alto, CA:2005. 1012843
  20. Dong, P., 2001, "Residual Stress Analyses of a Multi Pass Girth Weld : 3D-Special Shell Versus Axisymmetric Models," J. of Pressure Vessel Technology, Vol. 123, pp. 207-213 https://doi.org/10.1115/1.1359527
  21. Brickstad, B. and Josefson, B. L., 1998, "A Parametric Study of Residual Stresses in Multi Pass Butt Welded Stainless Steel Pipes," Int. J. Pres. Ves. & Piping, Vol. 75, pp. 11-25 https://doi.org/10.1016/S0308-0161(97)00117-8
  22. Elocate, C. D., Dennis, R. J., Bouchard, P. J. and Smith, M. C., 2005, "Three Dimensional Multi-Pass Repair Weld Simulations," Int. J. of Pres. Ves. & Piping, Vol. 82, pp. 244-257 https://doi.org/10.1016/j.ijpvp.2004.08.003
  23. ASME, 2004, Materials-Part D : Properties, AMSE Boiler and Pressure Vessel Code, Sec. II
  24. Special Metals Corporation, 2007, Inconel 600 & 690 information, www.specialmetals.com
  25. ABAQUS, 2003, "ABAQUS Standard/User's Manual, Version 6.4," Hibbit Karlsson & Sorensen, Inc
  26. Song,T.K., Bae,H.Y., Kim, Y.J., Lee, K.S. and Park, C.Y., 2008, "Sensitivity Analyses of Finite Element Method for Estimating Residual Stress of Dissimilar Metal Multi-Pass Welding," submitted to Trans. of the KSME(A)
  27. Dennis, R. J., Leggatt, N. A. and Gregg, A., 2006, "Optimisation of Weld Modeling Techniques-Bead on Plate Analysis," Trans. of ASME PVP, PVP2006- ICPVT-11-93907
  28. Brust, F. W. and Scott, P. M., 2007, "Weld Residual Stresses and Primary Water Stress Corrosion Cracking in Bimetal Nuclear Pipe Welds," Trans. of ASME PVP conference, PVP2007-26636
  29. Lee, S. H., Son, Y. H., Lee, J. H., Kim, W. S. and Yoon, S. C., 2007, "A Suggestion of Improvement Plan for ASME Sec. III Requirements Through the Construction Experience of Korea Standard Nuclear Power Plants(Hydrostatic test pressure and PWHT temperature of P-No. 4 materials)," Trans. of ASME PVP conference, PVP2007-26433
  30. ASME Code Case N-740, "Dissimilar Metal Weld Overlay for Repair of Class 1, 2, and 3 Items," ASME Boiler and Pressure Vessel Code, Sec. XI, Division I
  31. Timoshenko, S., 1956, Strength of Materials : Part II - Advanced Theory and Problems, D. Van Nostrand
  32. Materials Reliability Program : Welding Residual and Operating Stresses in PWR Alloy 182 Butt Welds (MRP-106), EPRI, Pal Alto, CA:2004. 1009378
  33. Courtin, S. and Gilles, P., 2006, "Detailed Simulation of an Overlay Repair on a 14” Dissimilar Material Weld," Trans. of ASME PVP conference, PVP2006-ICPVT-11-93823

Cited by

  1. Recent Study in Variation of Welding Materials for Overlay Welding vol.31, pp.6, 2013, https://doi.org/10.5781/KWJS.2013.31.6.17
  2. Stress Distribution in the Dissimilar Metal Butt Weld of Nuclear Reactor Piping due to the Simulation Technique for the Repair Welding vol.37, pp.5, 2013, https://doi.org/10.3795/KSME-A.2013.37.5.649
  3. Investigation into Variations of Welding Residual Stresses and Redistribution Behaviors for Different Repair Welding Widths vol.38, pp.2, 2014, https://doi.org/10.3795/KSME-A.2014.38.2.177
  4. Crack Growth Analysis due to PWSCC in Dissimilar Metal Butt Weld for Reactor Piping Considering Hydrostatic and Normal Operating Conditions vol.37, pp.1, 2013, https://doi.org/10.3795/KSME-A.2013.37.1.047
  5. Finite element analysis and measurement for residual stress of dissimilar metal weld in pressurizer safety nozzle mockup vol.23, pp.11, 2009, https://doi.org/10.1007/s12206-009-0809-2