Published June 1999 | Version v1
Journal article

Relationship between hardening and damage structure in austenitic stainless steel 316LN irradiated at low temperature in the HFIR

  • 1. Oak Ridge National Lab., TN (United States). Metals and Ceramics Div.
  • 2. Japan Atomic Energy Research Institute, Tokai-mura, Ibaraki-ken 319-11 (Japan)

Description

An austenitic stainless steel 316LN irradiated to damage levels of about 3 dpa at irradiation temperatures of about 90 C and 250 C has been examined by transmission electron microscopy. The irradiation at 90 C and 250 C induced a dislocation loop density of 3.5 x 1022 and 5.2 x 1022 m-3, and a black dot density of 2.2 x 1023 and 1.1 x 1023 m-3, respectively, in the steel. A low density (<1 x 1019 m-3) of radiation-enhanced precipitates was observed in the matrix. No cavities were observed. These features are correlated with the changes in tensile properties. It is concluded that the dislocation loops and the black dots cause irradiation hardening and a decrease in the uniform elongation in the 316LN steel irradiated at low temperatures. (orig.)

Additional details

Publishing Information

Journal Title
Journal of Nuclear Materials
Journal Volume
273
Journal Issue
1
Journal Page Range
p. 95-101
ISSN
0022-3115
CODEN
JNUMAM

Optional Information

Notes
29 refs.