Nuclear Engineering and Technology

Korean Nuclear Society (한국원자력학회)
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Fatigue crack growth characteristics of nitrogen-alloyed type 347 stainless steel under operating conditions of a pressurized water reactor

  • Min, Ki-Deuk (Korea Atomic Energy Research Institute, Nuclear Materials Safety Research Division) ;
  • Hong, Seokmin (Korea Atomic Energy Research Institute, Nuclear Materials Safety Research Division) ;
  • Kim, Dae-Whan (Korea Atomic Energy Research Institute, Nuclear Materials Safety Research Division) ;
  • Lee, Bong-Sang (Korea Atomic Energy Research Institute, Nuclear Materials Safety Research Division) ;
  • Kim, Seon-Jin (Hanyang University, Division of materials science and engineering)
  • Received : 2016.07.26
  • Accepted : 2017.01.25
  • Published : 2017.08.25
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Abstract

The fatigue crack growth behavior of Type 347 (S347) and Type 347N (S347N) stainless steel was evaluated under the operating conditions of a pressurized water reactor (PWR). These two materials showed different fatigue crack growth rates (FCGRs) according to the changes in dissolved oxygen content and frequency. Under the simulated PWR conditions for normal operation, the FCGR of S347N was lower than that of S347 and insensitive to the changes in PWR water conditions. The higher yield strength and better corrosion resistance of the nitrogen-alloyed Type 347 stainless steel might be a main cause of slower FCGR and more stable properties against changes in environmental conditions.

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