Numerical investigation on stress corrosion cracking behavior ofdissimilar weld joints in pressurized water reactor plants

Journal Title: Frattura ed Integrità Strutturale - Year 2014, Vol 8, Issue 29

Abstract

 There have been incidents recently where stress corrosion cracking (SCC) observed in the dissimilarmetal weld (DMW) joints connecting the reactor pressure vessel (RPV) nozzle with the hot leg pipe. Due to thecomplex microstructure and mechanical heterogeneity in the weld region, dissimilar metal weld joints are moresusceptible to SCC than the bulk steels in the simulated high temperature water environment of pressurizedwater reactor (PWR). Tensile residual stress (RS), in addition to operating loads, has a great contribution to SCCcrack growth. Limited experimental conditions, varied influence factors and diverging experimental data make itdifficult to accurately predict the SCC behavior of DMW joints with complex geometry, material configuration,operating loads and crack shape. Based on the film slip/dissolution oxidation model and elastic-plastic finiteelement method (EPFEM), an approach is developed to quantitatively predict the SCC growth rate of a RPVoutlet nozzle DMW joint. Moreover, this approach is expected to be a pre-analytical tool for SCC experiment ofDMW joints in PWR primary water environment.

Authors and Affiliations

Lingyan Zhao, He Xue, Fuqiang Yang, Yaohong Suo

Keywords

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  • EP ID EP110549
  • DOI 10.3221/IGF-ESIS.29.36
  • Views 57
  • Downloads 0

How To Cite

Lingyan Zhao, He Xue, Fuqiang Yang, Yaohong Suo (2014).  Numerical investigation on stress corrosion cracking behavior ofdissimilar weld joints in pressurized water reactor plants. Frattura ed Integrità Strutturale, 8(29), 410-418. https://europub.co.uk./articles/-A-110549