Relationship between hardening and damage structure in austenitic stainless steel 316LN irradiated at low temperature in the HFIR
Creators
- 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
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- Netherlands
- INIS RN
- 30031161
- Subject category
- S36: MATERIALS SCIENCE;
- Descriptors DEI
- AUSTENITIC STEELS; DISLOCATIONS; ELONGATION; PRECIPITATION; RADIATION HARDENING; STAINLESS STEELS; STRAINS; STRESSES; THERMONUCLEAR REACTOR MATERIALS; TRANSMISSION ELECTRON MICROSCOPY; YIELD STRENGTH
- Descriptors DEC
- ALLOYS; CARBON ADDITIONS; CRYSTAL DEFECTS; CRYSTAL STRUCTURE; DEFORMATION; ELECTRON MICROSCOPY; HARDENING; HIGH ALLOY STEELS; IRON ALLOYS; IRON BASE ALLOYS; LINE DEFECTS; MATERIALS; MECHANICAL PROPERTIES; MICROSCOPY; PHYSICAL RADIATION EFFECTS; RADIATION EFFECTS; SEPARATION PROCESSES; STEELS; TRANSITION ELEMENT ALLOYS
Optional Information
- Notes
- 29 refs.