Journal of Welding and Joining

The Korean Welding and Joining Society (대한용접접합학회)
권호 표지
DOI QR코드

DOI QR Code

Recent study of materials and welding methods for nuclear power plant

원자력발전 설비의 소재와 용접방법에 대한 최신 기술동향

  • 유호천 (한국과학기술정보연구원 ReSEAT 프로그램)
  • Received : 2014.12.24
  • Accepted : 2015.02.24
  • Published : 2015.02.28
Download PDF
⟨ Previous Next ⟩

Abstract

Recent developing tendency of nuclear power plant are studied by searching of NDSL, KIPRIS, Science Direct and so on. Welding materials such as low alloyed steels, stainless steels, nickel-based alloys, zirconium alloy and welding methods such as narrow gap welding, laser beam welding, friction stir welding, overlay welding are investigated.

Keywords

References

  1. Kameyama Masashi, Nuclear Power supply(Japan Nuclear Safety Institute), Journal of the Japan Welding Society, 82 (1) (2013), 57-63 (in Japanese) https://doi.org/10.2207/jjws.82.57
  2. Tohru Tobita et al., Effect of neutron irradiation on the mechanical properties of weld overlay cladding for reactor pressure vessel, Journal of Nuclear Materials 452 (2014), 61-68 https://doi.org/10.1016/j.jnucmat.2014.04.035
  3. C. Brillaud et al., Effects of radiation on materials: 20th International Symposium, ASTM STP 1405, American Society for Testing and Materials, West Conshohocken, (2001)
  4. Y. N. Korolev et al., Small specimens test techniques, Fourth volume, ASTM STP 1418, American Society for Testing and Materials, West Conshohocken (2002)
  5. A. Ulbricht et al., Small-angle neutron scattering investigation of as-irradiated, annealed and reirradiated reactor pressure vessel weld material of decommissioned react, Journal of Nuclear Materials, 416 (2011), 111-116 https://doi.org/10.1016/j.jnucmat.2010.12.219
  6. B. Gurovich et al., Evolution of weld metals nanostructure and properties under irradiation and recovery annealing of VVER-type reactors, Journal of Nuclear Materials, 434 (2013), 72-84 https://doi.org/10.1016/j.jnucmat.2012.11.026
  7. Kameyama Masashi, Nuclear power(Design), Journal of the Japan Welding Society, 83 (4) (2014), 270-274 (in Japanese) https://doi.org/10.2207/jjws.83.270
  8. K. Suzuki et al., Application of high strength MnMoNi steel to pressure vessels for nuclear power plant, Nuclear Engineering and Design, 206 (2001), 261-278 https://doi.org/10.1016/S0029-5493(00)00440-4
  9. Ryohei Ihara et al., Prediction of residual stress distributions due to surface machining and welding and crack growth simulation under residual stress distribution, Nuclear Engineering and Design, 241 (2011), 1335-1344 https://doi.org/10.1016/j.nucengdes.2011.01.018
  10. Ahmed Elmesalamy et al., A comparison of residual stresses in multi pass narrow gap laser welds and gas-tungsten arc welds in AISI 316L stainless steel, International Journal of Pressure Vessels and Piping, 113 (2014), 49-59 https://doi.org/10.1016/j.ijpvp.2013.11.002
  11. Y. Q. Wang et al., Localized Corrosion of Thermally Aged Cast Duplex Stainless Steel for Primary Coolant Pipes of Nuclear Power Plant, Procedia Engineering, 36 (2012), 88-95 https://doi.org/10.1016/j.proeng.2012.03.015
  12. T. Yonezawa, 2.08 Nickel Alloys, Properties and Characteris- tics, Tohoku University, Japan Elsevier Ltd. (2012), 233-266
  13. A. J. Ramirez et al., High temperature behavior of Ni-base weld metal Part II-insight into the mechanism for ductility dip cracking, Mater. Sci. Eng. A 380 (2004), 245-258 https://doi.org/10.1016/j.msea.2004.03.075
  14. A. J. Ramirez et al., Improving the ductility-dip cracking resistance of Ni-base alloys, J. Mater. Process. Technol. 179 (2006), 212-218 https://doi.org/10.1016/j.jmatprotec.2006.03.095
  15. In Chul Jung et al., Overlay Welding of Inconel Material for Nuclear Power Components, Journal of KWJS, 27 (2) (2009), 122-124
  16. Sung-Sik Kang et al., The experience and analysis of vent pipe PWSCC in PWR vessel head penetration, Nuclear Engineering and Design, 269 (2014), 291-298 https://doi.org/10.1016/j.nucengdes.2013.08.043
  17. http://www.meti.go.jp/committe/materials2/, Ministry of Economy, Trade and Industry homepage, download-files/g100121a05j.pdf
  18. Hwa Teng Lee et al., Numerical and experimental investigation into effect of temperature field on sensitization of Alloy 690 butt welds fabricated by gas tungsten arc welding and laser beam welding, Journal of Materials Processing Technology, 210 (2010), 1636-1645 https://doi.org/10.1016/j.jmatprotec.2010.05.012
  19. Seong Sik Hwang et al., Review of PWSCC and mitigation management strategies of Alloy 600 materials of PWRs, Journal of Nuclear Materials, 443 (2013), 321-330 https://doi.org/10.1016/j.jnucmat.2013.07.032
  20. S. M. Bruemmer et al., Characterization of defects in alloy 52, 152 and 52M welds, in: Proc. 14th Int. Conf. on Environmental Degradation of Materials in Nuclear Power Systems, ANS, LaGrange Park, IL, (2009), 319-332.
  21. A. J. Ramirez et al., Improving the ductility-dip cracking resistance of Ni-base alloys, J. Mater. Process. Technol. 179 (2006), 212-218 https://doi.org/10.1016/j.jmatprotec.2006.03.095
  22. L. Li, R. W. Messler Jr., Metall. Mater. Trans. A-Phys. Metall. Mater. Sci. 33A (2002) 2031-2042
  23. Qunjia Peng et al., Effect of chemical composition on grain boundary microchemistry and stress corrosion cracking in Alloy 182, Corrosion Science, 67 (2013) 91-99 https://doi.org/10.1016/j.corsci.2012.10.012
  24. M. K. Samal et al., Investigation of failure behavior of two different types of Zircaloy clad tubes used as nuclear reactor fuel pins, Engineering Failure Analysis, 18 (2011), 2042-2053 https://doi.org/10.1016/j.engfailanal.2011.06.009
  25. N. Boutarek et al., Microstructure change in the interface of CO2 laser welded zirconium alloys, Physics Procedia, 2 (2009), 1159-1165 https://doi.org/10.1016/j.phpro.2009.11.078
  26. Yong-Ding Lin et al., Effects of beam offset on mechanical properties and corrosion resistance of Alloy 690-SUS 304L EBW joints for nuclear power plant, Journal of Nuclear Materials, 401 (2010), 78-85 https://doi.org/10.1016/j.jnucmat.2010.04.001
  27. Wanjae Kim et al., Parametric study for Welding Residual Stresses in Nozzle of Nuclear Power Plants using Finite Element Method, Autumn Annual Meeting of The Korean Society of Mechanical Engineers, (2008), 104-109 (in Korean)
  28. Q. Peng et al., SCC behavior in the transition region of an Alloy 182, SA508 Cl.2 dissimilar weld joint under simulated BWR-NWC conditions, Proceedings of the 12th International Conference on Environmental Degradation of Materials in Nuclear Power System, Water Reactors, (2005), 589-599
  29. T. R. Allen et al., Proceedings of the 12th International Conference on Environmental Degradation of Materials in Nuclear Power System, Water Reactors, (2005), 833-842
  30. G. S. Was et al., Proceedings of the 11th International Conference on Environmental Degradation of Materials in Nuclear Power System, Water Reactors, (2003), 1071-1081
  31. J. Y. Huang et al., Effects of heat treatment and chromium content on the environmentally assisted cracking behavior of the dissimilar metal welds in simulated BWR coolant environments, Corrosion Science, 75 (2013), 386-399 https://doi.org/10.1016/j.corsci.2013.06.022
  32. D. J. Paraventi et al., Assessment of the interaction of variables in the intergranular stress corrosion crack growth rate behavior of alloys 600, 82, and 182, The 13th International Conference on Environmental Degradation of Materials in Nuclear Power Systems, (2007), 19-23
  33. J. Y. Huang et al., Effects of heat treatment and chromium content on the environmentally assisted cracking behavior of the dissimilar metal welds in simulated BWR coolant environments, Corrosion Science, 75 (2013), 386-399 https://doi.org/10.1016/j.corsci.2013.06.022
  34. Lee, Byoung-Hoon et al., Welding Technology and Application in Nuclear Power Plant,, Machinery and Materials, 19-1 (2007), 30-39 (in Korean)
  35. Nikulina A. V, Zirconium alloys in nuclear power engineering, Met Sci Heat Treat, 46 (11-12), (2004) 458-462 https://doi.org/10.1007/s11041-005-0002-x
  36. Seung Wan Woo et al., The Application of Narrow-Gap Welding Process for SA 106 Gr.C in Nuclear Power Plant, Autumn Annual Meeting of The Korean Society of Mechanical Engineers, (2014), 96-101 (in Korean)
  37. A. Traidia et al., On the effects of gravity and sulfur content on the weld shape in horizontal narrow gap GTAW of stainless steels, Journal of Materials Processing Technology, 213 (2013), 1128-1138 https://doi.org/10.1016/j.jmatprotec.2013.01.010
  38. Long Tan et al., Effect of geometric construction on residual stress distribution indesigning a nuclear rotor joined by multipass narrow gap welding, Fusion Engineering and Design, 89 (2014), 456-465 https://doi.org/10.1016/j.fusengdes.2014.03.080
  39. C. Liu et al., Numerical investigation on residual stress distribution and evolution during multipass narrow gap welding of thick-walled stainless steel pipes, Fusion Engineering and Design, 86-4 (2011), 288-295 https://doi.org/10.1016/j.fusengdes.2011.01.116
  40. P. D. Gupta et al., Laser Applications in Indian Nuclear Power Programme, Energy Procedia,7 (2011), 560-576 https://doi.org/10.1016/j.egypro.2011.06.077
  41. Gilner, A. et al., Laser applications in microtechnology, JMPT, 167 (2005), 494-498
  42. Kim, D. J et al., Repair welding of etched tubular components of nuclear power plant by Nd:YAG laser, JMPT, 14 (2001), 51-56
  43. Zhang X et al., Welding of thick stainless steel plates up to 50mm with high brightness lasers, Journal of Laser Appl. 23:022002, (2011) https://doi.org/10.2351/1.3567961
  44. Y. C. Chen et al., Banded structure and its distribution in friction stir processing of 316L austenitic stainless steel, Journal of Nuclear Materials, 420 (2012), 497-500 https://doi.org/10.1016/j.jnucmat.2011.10.053
  45. Lars Cederqvist et al., Reliability study of friction stir welded copper canisters containing Sweden's nuclear waste, Reliability Engineering and System Safety, 93 (2008), 1491-1499 https://doi.org/10.1016/j.ress.2007.09.010
  46. Tanigawa et al., Technical issues of reduced activation ferritic/martensitic steels for fabrication of ITER test blanket modules, Fusion Engineering and Design, 83 (2008), 1471-1476 https://doi.org/10.1016/j.fusengdes.2008.07.024
  47. E. Rajendra Kumar et al., Preliminary design of Test Blanket Module for ITER, Fusion Engineering and Design, 83 (2008), 1169-1172 https://doi.org/10.1016/j.fusengdes.2008.07.030
  48. Baldev Raj et al, Development of Reduced Activation Ferritic-Martensitic Steels and fabrication technologies for Indian test blanket module, Journal of Nuclear Materials, 417 (2011), 72-76 https://doi.org/10.1016/j.jnucmat.2011.02.032
  49. Y. Poitevin et al., Development of welding technologies for the manufacturing of European Tritium Breeder blanket modules, Journal of Nuclear Materials, 417 (2011), 36-42 https://doi.org/10.1016/j.jnucmat.2010.12.259
  50. MPR Associates, INC. Internal mechanical stress improvement method for mitigating stress corrosion cracking in weld areas of nuclear power plant piping, WO2014/012116, (2014)

Cited by

  1. Characteristics of GMAW Narrow Gap Welding on the Armor Steel of Combat Vehicles vol.7, pp.7, 2017, https://doi.org/10.3390/app7070658