Published March 1, 2004
| Version v1
Journal article
Irradiation damage in 304 and 316 stainless steels: experimental investigation and modeling. Part I: Evolution of the microstructure
Description
Irradiation damage in three austenitic stainless steels, SA 304L, CW 316 and CW Ti-modified 316, is investigated both experimentally and theoretically. The density and size of Frank loops after irradiation at 320 and 375 deg. C in experimental EBR II, BOR-60 and OSIRIS reactors for doses up to 40 dpa are characterized by TEM. The evolution of the initial dislocation network under irradiation is evaluated. A cluster dynamics model is proposed to account quantitatively for the experimental findings
Additional details
Identifiers
- DOI
- 10.1016/j.jnucmat.2003.11.007;
- PII
- S0022311503005129;
Publishing Information
- Journal Title
- Journal of Nuclear Materials
- Journal Volume
- 326
- Journal Issue
- 1
- Journal Page Range
- p. 19-29
- ISSN
- 0022-3115
- CODEN
- JNUMAM
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 35059617
- Subject category
- S36: MATERIALS SCIENCE;
- Descriptors DEI
- BOR-60 REACTOR; DENSITY; DISLOCATIONS; EBR-2 REACTOR; MICROSTRUCTURE; OSIRIS REACTOR; PHYSICAL RADIATION EFFECTS; RADIATION DOSES; SIMULATION; SIZE; STAINLESS STEEL-304L; STAINLESS STEEL-316; TEMPERATURE RANGE 0400-1000 K; TRANSMISSION ELECTRON MICROSCOPY
- Descriptors DEC
- ALLOYS; AUSTENITIC STEELS; BREEDER REACTORS; CARBON ADDITIONS; CHROMIUM ALLOYS; CHROMIUM STEELS; CHROMIUM-MOLYBDENUM STEELS; CHROMIUM-NICKEL STEELS; CHROMIUM-NICKEL-MOLYBDENUM STEELS; CORROSION RESISTANT ALLOYS; CRYSTAL DEFECTS; CRYSTAL STRUCTURE; DOSES; ELECTRON MICROSCOPY; ENRICHED URANIUM REACTORS; EPITHERMAL REACTORS; EXPERIMENTAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; HEAT RESISTANT MATERIALS; HEAT RESISTING ALLOYS; HIGH ALLOY STEELS; IRON ALLOYS; IRON BASE ALLOYS; IRRADIATION REACTORS; LINE DEFECTS; LIQUID METAL COOLED REACTORS; LMFBR TYPE REACTORS; LOW CARBON-HIGH ALLOY STEELS; MATERIALS; MATERIALS TESTING REACTORS; MICROSCOPY; MOLYBDENUM ALLOYS; NICKEL ALLOYS; PHYSICAL PROPERTIES; POWER REACTORS; RADIATION EFFECTS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; SODIUM COOLED REACTORS; STAINLESS STEELS; STEEL-CR17NI12MO3; STEEL-CR19NI10-L; STEELS; TANK TYPE REACTORS; TEMPERATURE RANGE; THERMAL REACTORS; TRANSITION ELEMENT ALLOYS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Copyright
- Copyright (c) 2003 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.