Preliminary Stress Corrosion Cracking Modeling Study of a Dissimilar Material Weld of Alloy (Inconel) 182 with Stainless Steel 316 in Pressurized Water Nuclear Reactor

Authors

  • Omar Fernandes Aly Nuclear Engineering Center, IPEN/CNEN-USP, São Paulo, Brazil
  • Miguel Mattar Neto Nuclear Engineering Center, IPEN/CNEN-USP, São Paulo, Brazil
  • Mônica Maria de Abreu Mendonça Schvartzman CDTN/CNEN-UFMG, Belo Horizonte, Brazil

DOI:

https://doi.org/10.6000/1929-6002.2014.03.04.9

Keywords:

Dissimilar Welds, Pressurized Water Stress Corrosion Cracking, Semi-Empiric-Probabilistic Modeling, Slow Strain Rate Tests, Weld Nickel Alloys (Inconel) 82/182

Abstract

Dissimilar welds (DW) are normally used in many components junctions in structural project of PWR (Pressurized Water Reactors) in Nuclear Plants. One had been departed of a DW of a nozzle located at a Reactor Pressure Vessel (RPV) of a PWR reactor, that joins the structural vessel material with an A316 stainless steel safe end. This weld is basically done with Inconel/Alloy 182 with a weld buttering of Inconel/Alloy 82. It had been prepared some axial cylindrical specimens retired from the Alloy 182/A316 weld end to be tested in the slow strain rate test machine located at CDTN laboratory. Based in these stress corrosion susceptibility results, it was done a preliminary semi-empiric modeling application to study the failure initiation time evolution of these specimens. The used model is composed by a deterministic part, and a probabilistic part according to the Weibull distribution. It had been constructed a specific Microsoft Excel worksheet to do the model application of input data. The obtained results had been discussed according with literature and also the model application limits.

References

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Published

2014-12-08

How to Cite

Aly, O. F., Neto, M. M., & de Abreu Mendonça Schvartzman, M. M. . . (2014). Preliminary Stress Corrosion Cracking Modeling Study of a Dissimilar Material Weld of Alloy (Inconel) 182 with Stainless Steel 316 in Pressurized Water Nuclear Reactor. Journal of Technology Innovations in Renewable Energy, 3(4), 221–226. https://doi.org/10.6000/1929-6002.2014.03.04.9

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