SCC Inhibitors for SG Tube Materials in Nuclear Power Plants

  • Kim, Kyung-Mo (Department of Nuclear Materials Technology Development, Korea Atomic Energy Research Institute) ;
  • Lee, Eun-Hee (Department of Nuclear Materials Technology Development, Korea Atomic Energy Research Institute) ;
  • Kim, Uh-Chul (Department of Nuclear Materials Technology Development, Korea Atomic Energy Research Institute)
  • Published : 2006.09.24

Abstract

Several chemicals were studied to suppress the damage due to stress corrosion cracking (SCC) of steam generator (SG) tubes in nuclear power plants. The effects on the SCC of the compounds, $TiO_2$, TyzorLA and $CeB_6$, were tested for several types of SG tubing materials. The test with the addition of $TiO_2$ and $CeB_6$ showed an effect in decreasing the SCC for the SG tubing material. However, $CeB_6$ caused some more SCC for Alloy 800. The penetration property into a crevice of the inhibitors was investigated by using Alloy 600 specimens with different gap.

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