Published 1992 | Version v1
Book

An IASCC study using high energy ion irradiation

  • 1. Toshiba Corp., Yokohama (Japan)
  • 2. Hitachi Ltd., Ibaraki (Japan)
  • 3. Tokyo Electric Power Co. (Japan)

Description

High energy ion irradiation to simulate neutron damage was applied to study the irradiation effect on stress corrosion cracking (SCC) in stainless steels. Small tensile specimens of commercial purity type 304, high purity type 304L (HP304L) and high purity type 304L containing phosphorus (HP304L+P) were irradiated with 60 MeV He2+ ions by using a cyclotron at 560-580 K, up to a dose of 0.4 dpa. Slow strain rate tests (SSRT) were conducted in high temperature water containing 32 ppm dissolved oxygen (DO). No intergranular SCC was observed on 304 irradiated up to 0.4 dpa. HP304L and HP304L+P irradiated to 0.4 dpa failed by intergranular SCC and exhibited greater increases in yield strength. The results show that simulation irradiation is a potential method for use to study IASCC. Displacement damage by irradiation is essential for the occurrence of IASCC. The different response to the irradiation among the alloys was attributed to their impurity contents and damage characteristics of ion irradiation

Additional details

Publishing Information

Publisher
American Nuclear Society, Inc.
Imprint Place
La Grange Park, IL (United States)
Imprint Title
Proceedings of the fifth international symposium on environmental degradation of materials in nuclear power systems - water reactors
Imprint Pagination
995 p.
Journal Page Range
p. 814-820.

Conference

Title
5. international symposium on environmental degradation of materials in nuclear power systems - water reactors.
Dates
25-29 Aug 1991.
Place
Monterey, CA (United States).

Optional Information

Secondary number(s)
CONF-910808--.