한국원자력학회:학술대회논문집 (Proceedings of the Korean Nuclear Society Conference)

한국원자력학회 (Korean Nuclear Society)
권호 표지

Environmentally Assisted Crack Growth Behavior of SA508 Cl.3 Pressure Vessel Steel

  • Kim, Jun-Hwan (Korea Advanced Institute of Science and Technology Department of nuclear Engineering) ;
  • Kim, In-Sup (Korea Advanced Institute of Science and Technology Department of nuclear Engineering)
  • 발행 : 1998.05.01
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초록

In order to assess the susceptibility of the environmentally assisted cracking(EAC) on SA508 Cl.3 steel in primary water condition, potential step test and slow strain rate test(SSRT) were conducted in a simulated crack tip condition. In this test, anodic dissolution was dominant in the crack tip environments. Proposed simple dissolution model is a modification of Hishida's anodic dissolution model at the plastic zone. One can predict actual crack growth rate with the smooth specimen through this model.

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