Published 2007 | Version v1
Miscellaneous

Deformation behavior around grain boundaries for SCC propagation in hardened low-carbon austenitic stainless steel by micro hardness test

  • 1. National Inst. for Materials Science (NIMS), Ibaraki (Japan)
  • 2. Japan Atomic Energy Agency (JAEA), Ibaraki (Japan)
  • 3. Japan Nuclear Energy Safety Organization (JNES), Tokyo (Japan)

Description

Stress corrosion cracking (SCC) was found in shroud and PLR piping made of low-carbon austenitic stainless steels in Japanese BWR plants. The intergranular type (IG) SCC propagated in hardened heat affected zones (HAZ) around welds. Strength behavior and local plastic deformation for a low-carbon austenitic stainless steel 316L, rolled at the reductions in area of 10, 30% at room temperature to simulate the hardened HAZ, were measured by a micro-hardness test machine and observed by atomic force microscopy (AFM), respectively. The tensile deformation at yield point (0.2% plastic strain) had given to the work-hardened 316L to simulate the plastic zone at the crack tip. It is suggested that one of the IGSCC propagation mechanism for 316L was related with the intergranular strength behavior and local plastic deformation around grain boundaries. (author)

Part of:
13th International conference on environmental degradation of materials in nuclear power systems

Additional details

Publishing Information

Publisher
Canadian Nuclear Society
Imprint Place
Toronto, Ontario (Canada)
ISBN
0-919784-89-5
Imprint Title
13th International conference on environmental degradation of materials in nuclear power systems
Imprint Pagination
388 Megabytes
Journal Page Range
[15 p.]

Conference

Title
13. International conference on environmental degradation of materials in nuclear power systems
Dates
19-23 Aug 2007
Place
Whistler, BC (Canada)

Optional Information

Notes
13 refs., 4 tabs., 12 figs.