Radiation-induced solute segregation
Description
Substitutional solute segregation in a face-centered-cubic metal under irradiation has been studied using a kinetic model. The model includes the effects of vacancy and dumbbell-interstitial diffusional encounters with solute atoms, diffusion of point defects and bound complexes, and spatially independent reaction terms. The GEAR package of subroutines, developed at Lawrence Livermore Laboratory, has been used for numerical solution of the resultant rate equations. Assuming thin-foil geometry and parameters appropriate for Zn in Ag, solute segregation is found to be significant in the temperature range from 0.2 to 0.6 T/sub m/, with maximum segregation occurring at approximately 0.45 T/sub m/. The temperature for maximum segregation is appreciably lower for reactor irradiation rates than for ion-bombardment or high-voltage electron-microscope irradiation rates. Segregation is also found to be maximum when the interstitial-solute binding energy is sufficiently high so that the migration energies of the vacancy and interstitial-solute complex become comparable
Additional details
Publishing Information
- Journal Title
- Nucl. Metall.
- Journal Volume
- 20
- Series
- Nucl. Metall.
- Journal Page Range
- 121-142
Conference
- Title
- Conference on computer simulation for materials applications.
- Dates
- 19 Apr 1976.
- Place
- Gaithersburg, Maryland, United States of America (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 8306012
- Subject category
- S36: MATERIALS SCIENCE;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COMPUTER CODES; FOILS; G CODES; INTERSTITIALS; PHYSICAL RADIATION EFFECTS; SEGREGATION; SILVER ALLOYS; ZINC ALLOYS
- Descriptors DEC
- ALLOYS; CRYSTAL DEFECTS; CRYSTAL STRUCTURE; POINT DEFECTS; RADIATION EFFECTS; TRANSITION ELEMENT ALLOYS
Optional Information
- Notes
- See CONF-760421--P1.