Microchemical change and grain boundary migration due to excess defects flow under irradiation
Creators
- 1. Hokkaido Univ., Sapporo (Japan). Faculty of Engineering
Description
A Fe-Cr-Ni model alloy was electron-irradiated using a high voltage electron microscopy (1000kV), and in situ observation on structural evolution and microchemical analyses were carried out. When the Fe-Cr-Ni alloy was irradiated, the nucleation of dislocation loops followed by voids was observed and at the same time a grain boundary migration occurred. The compositional analysis after irradiation of an area including a grain boundary indicated nickel enrichment and chromium depletion near the grain boundary. It is suggested that when the radiation -induced point defects flow into the grain boundary, boundary migration and solutes redistribution are induced and the magnitudes depend on net point defects flow, especially that of interstitial atoms. The microchemical changes were also simulated by model calculation. (author)
Additional details
Publishing Information
- Publisher
- Japanese Society of Materials for Advanced Energy Systems.
- Imprint Place
- Tokyo (Japan)
- Imprint Title
- Materials for advanced energy systems and fission and fusion engineering '94. Proceedings of the second Japan/China symposium
- Imprint Pagination
- 501 p.
- Journal Page Range
- p. 386-391.
Conference
- Title
- 2. Japan/China symposium on materials for advanced energy systems and fission and fusion engineering.
- Dates
- 5-8 Jun 1994.
- Place
- Tokyo (Japan).
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 27021643
- Subject category
- S36: MATERIALS SCIENCE; S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CHEMICAL ANALYSIS; CONCENTRATION RATIO; DOSE-RESPONSE RELATIONSHIPS; ELECTRON BEAMS; ELECTRON MICROSCOPY; ELEMENT ABUNDANCE; GRAIN BOUNDARIES; MIGRATION; NUCLEATION; PHYSICAL RADIATION EFFECTS; POINT DEFECTS; SCREW DISLOCATIONS; SPATIAL DISTRIBUTION; STAINLESS STEEL-316; TEMPERATURE DEPENDENCE; TEMPERATURE RANGE 0400-1000 K; THERMONUCLEAR REACTOR MATERIALS; VOIDS
- Descriptors DEC
- ABUNDANCE; ALLOYS; AUSTENITIC STEELS; BEAMS; CARBON ADDITIONS; CHROMIUM ALLOYS; CHROMIUM STEELS; CHROMIUM-MOLYBDENUM STEELS; CHROMIUM-NICKEL STEELS; CHROMIUM-NICKEL-MOLYBDENUM STEELS; CORROSION RESISTANT ALLOYS; CRYSTAL DEFECTS; CRYSTAL STRUCTURE; DISLOCATIONS; DISTRIBUTION; HEAT RESISTANT MATERIALS; HEAT RESISTING ALLOYS; HIGH ALLOY STEELS; IRON ALLOYS; IRON BASE ALLOYS; LEPTON BEAMS; LINE DEFECTS; MATERIALS; MICROSCOPY; MICROSTRUCTURE; MOLYBDENUM ALLOYS; NICKEL ALLOYS; PARTICLE BEAMS; RADIATION EFFECTS; STAINLESS STEELS; STEEL-CR17NI12MO3; STEELS; TEMPERATURE RANGE; TRANSITION ELEMENT ALLOYS