Published 1976 | Version v1
Journal article

Radiation-induced solute segregation

  • 1. Argonne National Lab., IL

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.