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Title: Interdiffusion and reaction between pure magnesium and aluminum alloy 6061

Using solid-to-solid couples investigation, this study characterized the reaction products evolved and quantified the diffusion kinetics when pure Mg bonded to AA6061 is subjected to thermal treatment at 300°C for 720 hours, 350°C for 360 hours, and 400°C for 240 hours. Characterization techniques include optical microscopy, scanning electron microscopy with X-ray energy dispersive spectroscopy, and transmission electron microscopy. Parabolic growth constants were determined for γ-Mg 17Al 12, β-Mg 2Al 3, and the elusive ε-phase. Similarly, the average effective interdiffusion coefficients of major constituents were calculated for Mg (ss), γ-Mg 17Al 12, β-Mg 2Al 3, and AA6061. The activation energies and pre-exponential factors for both parabolic growth constant and average effective interdiffusion coefficients were computed using the Arrhenius relationship. The activation energy for growth of γ-Mg 17Al 12 was significantly higher than that for β-Mg 2Al 3 while the activation energy for interdiffusion of γ-Mg 17Al 12 was only slightly higher than that for β-Mg 2Al 3. As a result, comparisons are made between the results of this study and those of diffusion studies between pure Mg and pure Al to examine the influence of alloying additions in AA6061.
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  1. Univ. of Central Florida, Orlando, FL (United States)
  2. Idaho National Lab. (INL), Idaho Falls, ID (United States)
Publication Date:
Report Number(s):
Journal ID: ISSN 1662-9507
Grant/Contract Number:
Accepted Manuscript
Journal Name:
Defect and Diffusion Forum (Online)
Additional Journal Information:
Journal Name: Defect and Diffusion Forum (Online); Journal Volume: 364; Journal ID: ISSN 1662-9507
Trans Tech Publications
Research Org:
Idaho National Lab. (INL), Idaho Falls, ID (United States)
Sponsoring Org:
USDOE National Nuclear Security Administration (NNSA)
Country of Publication:
United States
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; diffusion; low enriched uranium; magnesium; nuclear fuel; interdiffusion; reaction; AA6061; electron microscopy
OSTI Identifier: