Deformation temperature, strain rate, and irradiation microstructure effects on localized plasticity in 304L SS
- 1. Washington State Univ., Richland, WA (United States)
- 2. Pacific Northwest Lab., Richland, WA (United States)
Description
The present study examines the deformation behavior of ion-irradiated, low-carbon 304L stainless steel to investigate the influence of irradiation microstructure, deformation temperature and strain rate on localized plasticity. Dislocation loop character, size and density are linked to changes in deformation character. Lower doses produce small faulted loops and stacking fault tetrahedra that impede dislocation mobility. Dislocations are pinned at defects and require higher stress to break free from the defects. Larger defects take the form of faulted Frank loops that can interact with glide dislocations to form microtwins at lower temperatures and faster strain rates. Deformation at higher temperatures and slower strain rates promotes interactions between glide dislocations and loops leading to loop annihilation. Dislocation free zones or ''channels'' form where further plastic deformation is highly localized. Results are compared to limited observations for neutron-irradiated materials. These irradiation-induced changes can be an important concern for light-water reactor (LWR) stainless steel (SS) structural components due to a reduced damage tolerance, and potential susceptibility to environmental cracking such as irradiation-assisted stress corrosion cracking (IASCC)
Additional details
Publishing Information
- Publisher
- NACE International.
- Imprint Place
- Houston, TX (United States)
- ISBN
- 1-877914-95-9
- Imprint Title
- Seventh international symposium on environmental degradation of materials in nuclear power systems -- Water reactors: Proceedings and symposium discussions. Volume 2
- Imprint Pagination
- 620 p.
- Journal Page Range
- p. 817-826.
Conference
- Title
- water reactors.
- Acronym
- 7. NACE international symposium on environmental degradation of materials in nuclear power plants
- Dates
- 6-10 Aug 1995.
- Place
- Breckenridge, CO (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 27043644
- Subject category
- S36: MATERIALS SCIENCE; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Numerical Data
- Descriptors DEI
- CRACK PROPAGATION; CRYSTAL DEFECTS; EXPERIMENTAL DATA; PHYSICAL RADIATION EFFECTS; RADIATION DOSES; REACTOR MATERIALS; STAINLESS STEEL-304L; WATER COOLED REACTORS
- Descriptors DEC
- ALLOYS; AUSTENITIC STEELS; CARBON ADDITIONS; CHROMIUM ALLOYS; CHROMIUM-NICKEL STEELS; CORROSION RESISTANT ALLOYS; CRYSTAL STRUCTURE; DATA; HEAT RESISTANT MATERIALS; HEAT RESISTING ALLOYS; HIGH ALLOY STEELS; INFORMATION; IRON ALLOYS; IRON BASE ALLOYS; LOW CARBON-HIGH ALLOY STEELS; MATERIALS; NICKEL ALLOYS; NUMERICAL DATA; RADIATION EFFECTS; REACTORS; STAINLESS STEELS; STEEL-CR19NI10-L; STEELS; TRANSITION ELEMENT ALLOYS
Optional Information
- Secondary number(s)
- CONF-950816--.