Journal of Phase Equilibria and Diffusion

, Volume 34, Issue 4, pp 307–312 | Cite as

Interdiffusion Between Potential Diffusion Barrier Mo and U-Mo Metallic Fuel Alloy for RERTR Applications

Research Article
First Online:
Received:
Revised:

Abstract

U-Mo alloys are being developed as low enrichment uranium fuels under the Reduced Enrichment for Research and Test Reactor Program. Previous investigation has shown that the interdiffusion between U and Mo in γ(bcc)-U solid solution is very slow. This investigation explored interdiffusional behavior, especially in regions with high Mo concentration, and the potential application of Mo as a barrier material to reduce the interaction between U-Mo fuel and Al alloys matrix. Solid-to-solid U-10wt.%Mo versus Mo diffusion couples were assembled and annealed at 600, 700, 800, 900 and 1000 °C for 960, 720, 480, 240, 96 h, respectively. The interdiffusion microstructures and concentration profiles were examined via scanning electron microscopy and electron probe microanalysis, respectively. As the Mo concentration increased from 22 to 32 at.%, the interdiffusion coefficient decreased while the activation energy increased. The growth rate constant of the interdiffusion zone between U-10wt.%Mo versus Mo was also determined and compared to be 104-105 times lower than those of U-10wt.%Mo versus Al and U-10wt.%Mo versus Al-Si systems. Other desirable physical properties of Mo as a barrier material, such as neutron adsorption rate, melting point and thermal conductivity, are also highlighted.

Keywords

binary diffusion Boltzmann/Matano analysis diffusion couples diffusivity measurements 
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Notes

Acknowledgments

This work was supported by the U.S. Department of Energy, Office of Nuclear Materials Threat Reduction (NA-212), National Nuclear Security Administration, under DOE-NE Idaho Operations Office Contract DE-AC07-05ID14517. Accordingly, the U.S. Government retains a non-exclusive, royalty-free license to publish or reproduce the published form of this contribution, or allow others to do so, for U.S. Government purposes. Authors also acknowledge the editorial review and revision contribution from Ms. Megan A. Boye.

References

  1. 1.
    D. Keiser, S. Hayes, M. Meyer, and C. Clark, High-Density, Low-Enriched Uranium Fuel for Nuclear Research Reactors, JOM, 2003, 55, p 55–58CrossRefGoogle Scholar
  2. 2.
    J.L. Snelgrove, G.L. Hofman, M.K. Meyer, C.L. Trybus, and T.C. Wiencek, Development of Very-High-Density Low-Enriched-Uranium Fuels, Nucl. Eng. Des., 1997, 178, p 119–126CrossRefGoogle Scholar
  3. 3.
    D. Wachs, D. Keiser, M. Meyer, D. Burkes, C. Clark, G. Moore, J.-F. Jue, T. Totev, G. Hofman, T. Wiencek, Y.S. Kim, and J. Snelgrove, High Density Fuel Development for Research Reactors, Global 2007-Advanced Nuclear Fuel Cycles and Systems, 2007Google Scholar
  4. 4.
    M.K. Meyer, G.L. Hofman, S.L. Hayes, C.R. Clark, T.C. Wiencek, J.L. Snelgrove, R.V. Strain, and K.H. Kim, Low-Temperature Irradiation Behavior of Uranium-Molybdenum Alloy Dispersion Fuel, J. Nucl. Mater., 2002, 304, p 221–236ADSCrossRefGoogle Scholar
  5. 5.
    A. Leenaers, S. Van den Berghe, E. Koonen, C. Jarousse, F. Huet, M. Trotabas, M. Boyard, S. Guillot, L. Sannen, and M. Verwerft, Post-irradiation Examination of Uranium-7 wt% Molybdenum Atomized Dispersion Fuel, J. Nucl. Mater., 2004, 335, p 39–47ADSCrossRefGoogle Scholar
  6. 6.
    E. Perez, B. Yao, D.D. Keiser, and Y.H. Sohn, Microstructural Analysis of As-Processed U-10 wt.%Mo Monolithic Fuel Plate in AA6061 Matrix with Zr Diffusion Barrier, J. Nucl. Mater., 2010, 402, p 8–14ADSCrossRefGoogle Scholar
  7. 7.
    D.D. Keiser, J.F. Jue, B. Yao, E. Perez, Y. Sohn, and C.R. Clark, Microstructural Characterization of U-7Mo/Al-Si Alloy Matrix Dispersion Fuel Plates Fabricated at 500 Degrees C, J. Nucl. Mater., 2011, 412, p 90–99ADSCrossRefGoogle Scholar
  8. 8.
    B. Yao, E. Perez, D.D. Keiser, Jr., J.-F. Jue, C.R. Clark, N. Woolstenhulme, and Y. Sohn, Microstructure Characterization of As-Fabricated and 475 °C Annealed U-7 wt.% Mo Dispersion Fuel in Al-Si Alloy Matrix, J. Alloy. Compd., 2011, 509, p 9487–9496CrossRefGoogle Scholar
  9. 9.
    E. Perez, D. Keiser, and Y. Sohn, Phase Constituents and Microstructure of Interaction Layer Formed in U-Mo Alloys vs Al Diffusion Couples Annealed at 873 K (600 °C), Metall. Mater. Trans. A, 2011, 42, p 3071–3083CrossRefGoogle Scholar
  10. 10.
    A. Leenaers, S. Van den Berghe, W. Van Renterghem, F. Charollais, P. Lemoine, C. Jarousse, A. Rohrmoser, and W. Petry, Irradiation Behavior of Ground U(Mo) Fuel With and Without Si Added to the Matrix, J. Nucl. Mater., 2011, 412, p 41–52ADSCrossRefGoogle Scholar
  11. 11.
    X. Liu, T.C. Lu, Z.H. Xing, and D.Z. Qian, Effects of Different Irradiation Conditions on Swelling Performance of U(10)Mo-Al Dispersion Fuel, Rare Met. Mater. Eng., 2011, 40, p 1125Google Scholar
  12. 12.
    F. Mazaudier, C. Proye, and F. Hodaj, Further Insight into Mechanisms of Solid-State Interactions in UMo/Al System, J. Nucl. Mater., 2008, 377, p 476–485ADSCrossRefGoogle Scholar
  13. 13.
    C. Komar Varela, M. Mirandou, S. Aricó, S. Balart, and L. Gribaudo, Interdiffusion Between U(Mo,Pt) or U(Mo,Zr) and Al or Al A356 Alloy, J. Nucl. Mater., 2009, 395, p 162–168ADSCrossRefGoogle Scholar
  14. 14.
    Y. Kim, G. Hofman, H. Ryu, and S. Hayes, Irradiation-Enhanced Interdiffusion in the Diffusion Zone of U-Mo Dispersion Fuel in Al, J. Phase Equilib. Diffus., 2006, 27, p 614–621Google Scholar
  15. 15.
    H. Ryu, J. Park, C. Kim, Y. Kim, and G. Hofman, Diffusion Reaction Behaviors of U-Mo/Al Dispersion Fuel, J. Phase Equilib. Diffus., 2006, 27, p 651–658Google Scholar
  16. 16.
    K. Huang, D.D. Keiser, Jr., and Y.H. Sohn, Interdiffusion, Intrinsic Diffusion, Atomic Mobility, and Vacancy Wind Effects in γ(bcc) Uranium-Molybdenum Alloy, Metall. Mater. Trans. A, 2013, 44A, p 738–746ADSCrossRefGoogle Scholar
  17. 17.
    E.A. Brandes and G.B. Brook, Ed., Smithells Metals Reference Book, 1992Google Scholar
  18. 18.
    J.R. Davis, Ed., ASM Handbook Volume 2: Properties and Selection: Nonferrous Alloys and Special-Purpose Materials, ASM International, Materials Park, OH, 1992Google Scholar
  19. 19.
    K. Huang, Y. Park, A. Ewh, B.H. Sencer, J.R. Kennedy, K.R. Coffey, and Y.H. Sohn, Interdiffusion and Reaction Between Uranium and Iron, J. Nucl. Mater., 2012, 424, p 82–88ADSCrossRefGoogle Scholar
  20. 20.
    C. Wagner, The Evaluation of Data Obtained with Diffusion Couples of Binary Single-Phase and Multiphase Systems, Acta Metall., 1969, 17, p 99–107CrossRefGoogle Scholar
  21. 21.
    P. Shewmon, Diffusion in Solids, Wiley, New York, 1989Google Scholar
  22. 22.
    E. Perez, D.D.J. Keiser, B. Yao, and Y.H. Sohn, Interdiffusion in Diffusion Couples: U-Mo v. Al and Al-Si, RERTR 2009 Beijing, China, 2009Google Scholar

Copyright information

© ASM International 2013

Authors and Affiliations

  • K. Huang
    • 1
  • Y. Park
    • 1
  • D. D. KeiserJr.
    • 2
  • Y. H. Sohn
    • 1
  1. 1.Advanced Materials Processing and Analysis Center, Department of Mechanical, Materials and Aerospace EngineeringUniversity of Central FloridaOrlandoUSA
  2. 2.Nuclear Fuels and Materials DivisionIdaho National LaboratoryIdaho FallsUSA

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