skip to main content
OSTI.GOV title logo U.S. Department of Energy
Office of Scientific and Technical Information

Title: ATOMISTIC SIMULATION OF VACANCY AND SELF-INTERSTITIAL DIFFUSION IN Fe-Cu ALLOYS

Conference ·
DOI:https://doi.org/10.1557/PROC-650-R6.9· OSTI ID:15003262

Neutron hardening and embrittlement of pressure vessel steels is due to a high density of nanometer scale features, including Cu-rich precipitates which form as a result of radiation enhanced diffusion. High-energy displacement cascades generate large numbers of both isolated point defects and clusters of vacancies and interstitials. The subsequent clustering, diffusion and ultimate annihilation of primary damage is inherently coupled with solute transport and hence, the overall chemical and microstructural evolutions under irradiation. In this work, we present atomistic simulation results, based on many-body interatomic potentials, of the migration of vacancies, solute and self-interstitial atoms (SIA) in pure Fe and binary Fe-0.9 and 1.0 at.% Cu alloys. Cu diffusion occurs by a vacancy mechanism and the calculated Cu diffusivity is in good agreement with experimental data. Strain field interactions between the oversized substitutional Cu solute atoms and SIA and SIA clusters are predominantly repulsive and result in both a decreased activation energy and diffusion pre-factor for SIA and small (N < 5) SIA cluster migration, which occurs by three-dimensional motion. The Cu appears to enhance the reorientation of the SIA clusters to different <111> directions, as well as the transition from <110> to mobile <111> configurations. The migration behavior of larger SIA clusters, which undergo only one-dimensional diffusion during molecular dynamics timescales, is largely unaffected by the Fe-Cu alloy, although SIA clusters are effectively repelled by coherent Cu precipitates.

Research Organization:
Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)
Sponsoring Organization:
US Department of Energy (US)
DOE Contract Number:
W-7405-ENG-48
OSTI ID:
15003262
Report Number(s):
UCRL-JC-139405; TRN: US0402524
Resource Relation:
Journal Volume: 650; Conference: Materials Research Society Fall 2000 Symposium, Boston, MA (US), 11/27/2000--12/01/2000; Other Information: PBD: 25 Jan 2001
Country of Publication:
United States
Language:
English

References (8)

A computational microscopy study of nanostructural evolution in irradiated pressure vessel steels journal November 1997
Computer simulation of point defect properties in dilute Fe—Cu alloy using a many-body interatomic potential journal March 1997
Precipitation kinetics of dilute FeCu and FeCuMn alloys subjected to electron irradiation journal March 1992
Energetics of formation and migration of self-interstitials and self-interstitial clusters in α-iron journal April 1997
The diffusion and solubility of copper in iron journal May 1977
Monte Carlo simulations of copper precipitation in dilute iron-copper alloys during thermal ageing and under electron irradiation journal September 1996
On the dominant mechanism of irradiation embrittlement of reactor pressure vessel steels journal October 1983
Recent progress in understanding reactor pressure vessel steel embrittlement journal June 1998