STRESS CORROSION CRACK PROPAGATION BEHAVIOR OF DOMESTIC FORGED NUCLEAR GRADE 316L STAINLESS STEEL IN HIGH TEMPERATURE AND HIGH PRESSURE WATER

  • ZHANG Litao ,
  • WANG Jianqiu
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  • State Key Laboratory for Corrosion and Protection, Institute of Metal Research, Chinese Academy of Sciences,Shenyang 110016

Received date: 2013-04-08

  Revised date: 2013-05-15

  Online published: 2013-08-11

Abstract

Stress corrosion cracking growth rates of domestic forged nuclear grade 316L stainless steel (SS) were successfully measured in high temperature and high pressure water at various temperatures and under various loading mode. A direct current potential drop (DCPD) technique was used to monitor the crack growth throughout the test. The crack growth rate decreases with the increasing dissolved hydrogen content and the decreasing dissolved oxygen content. The crack growth rate under trapezoidal loading mode is bigger than that under constant loading. The fracture surface has typical intergranular stress corrosion cracking (IGSCC) characteristics.

Cite this article

ZHANG Litao , WANG Jianqiu . STRESS CORROSION CRACK PROPAGATION BEHAVIOR OF DOMESTIC FORGED NUCLEAR GRADE 316L STAINLESS STEEL IN HIGH TEMPERATURE AND HIGH PRESSURE WATER[J]. Acta Metall Sin, 2013 , 49(8) : 911 -916 . DOI: 10.3724/SP.J.1037.2013.00171

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