Fuel-Matrix Chemical Interaction between U-7wt.%Mo Alloy and Mg

Abstract:

A solid-to-solid, U-7wt.%Mo vs. Mg diffusion couple was assembled and annealed at 550°C for 96 hours. Themicrostructurein the interdiffusion zone and the development of concentration profiles were examined via scanning electron microscopy, transmission electron microscopy (TEM) and X-ray energy dispersive spectroscopy. A TEM specimen was prepared at the interface between U-7wt.%Mo andMgusing focused ion beam in-situ lift-out. The U-7wt.%Mo alloy was bonded well tothe Mg at the atomic scale, without any evidence of oxidation, cracks or pores.Despite the good bonding, very little or negligible interdiffusion was observed.This is consistent with the expectation based on negligible solubilities according to the equilibrium phase diagrams. Along with other desirableproperties, Mgis a potential inert matrix or barrier materialfor U-Mo fuel alloy systembeing developed forthe Reduced Enrichment for Research and Test Reactor (RERTR) program.

• Periodical: Defect and Diffusion Forum (Volume 333)
• Pages: 199-206
• DOI: https://doi.org/10.4028/www.scientific.net/DDF.333.199
• Online since: January 2013
• Authors: K. Huang, H. Heinrich, D.D. Keiser, Yong Ho Sohn
• Keywords: Diffusion Barrier, Interdiffusion, Mg, U-Mo Alloy

References

[1] Keiser D, Hayes S, Meyer M, Clark C. High-density, low-enriched uranium fuel for nuclear research reactors. JOM Journal of the Minerals, Metals and Materials Society 2003; 55: 55.

DOI: 10.1007/s11837-003-0031-0

[2] Snelgrove JL, Hofman GL, Meyer MK, Trybus CL, Wiencek TC. Development of very-high-density low-enriched-uranium fuels. Nuclear Engineering and Design 1997; 178: 119.

DOI: 10.1016/s0029-5493(97)00217-3

[3] Wachs D, Keiser D, Meyer M, Burkes D, Clark C, Moore G, Jue J-F, Totev T, Hofman G, Wiencek T, Kim YS, Snelgrove J. High density fuel development for research reactors. Global 2007-Advanced Nuclear Fuel Cycles and Systems, (2007).

[4] Meyer MK, Hofman GL, Hayes SL, Clark CR, Wiencek TC, Snelgrove JL, Strain RV, Kim KH. Low-temperature irradiation behavior of uranium-molybdenum alloy dispersion fuel. J Nucl Mater 2002; 304: 221.

DOI: 10.1016/s0022-3115(02)00850-4

[5] Leenaers A, Van den Berghe S, Koonen E, Jarousse C, Huet F, Trotabas M, Boyard M, Guillot S, Sannen L, Verwerft M. Post-irradiation examination of uranium-7 wt% molybdenum atomized dispersion fuel. J Nucl Mater 2004; 335: 39.

DOI: 10.1016/j.jnucmat.2004.07.004

[6] Perez E, Yao B, Keiser DD, Sohn YH. Microstructural analysis of as-processed U-10 wt. %Mo monolithic fuel plate in AA6061 matrix with Zr diffusion barrier. J Nucl Mater 2010; 402: 8.

DOI: 10.1016/j.jnucmat.2010.04.016

[7] Keiser DD, Jue JF, Yao B, Perez E, Sohn Y, Clark CR. Microstructural characterization of U-7Mo/Al-Si alloy matrix dispersion fuel plates fabricated at 500 degrees C. J Nucl Mater 2011; 412: 90.

DOI: 10.1016/j.jnucmat.2011.02.027

[8] Yao B, Perez E, Keiser Jr DD, Jue J-F, Clark CR, Woolstenhulme N, Sohn Y. Microstructure characterization of as-fabricated and 475 °C annealed U-7 wt. % Mo dispersion fuel in Al-Si alloy matrix. J. Alloys Compd. 2011; 509: 9487.

DOI: 10.1016/j.jallcom.2011.07.048

[9] Perez E, Keiser D, Sohn Y. 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: 3071.

DOI: 10.1007/s11661-011-0733-9

[10] Leenaers A, Van den Berghe S, Van Renterghem W, Charollais F, Lemoine P, Jarousse C, Rohrmoser A, Petry W. Irradiation behavior of ground U(Mo) fuel with and without Si added to the matrix. J Nucl Mater 2011; 412: 41.

DOI: 10.1016/j.jnucmat.2011.02.002

[11] Liu X, Lu TC, Xing ZH, Qian DZ. Effects of different irradiation conditions on swelling performance of U(10)Mo-Al dispersion fuel. Rare Metal Mat. Eng. 2011; 40: 1125.

[12] Mazaudier F, Proye C, Hodaj F. Further insight into mechanisms of solid-state interactions in UMo/Al system. J Nucl Mater 2008; 377: 476.

DOI: 10.1016/j.jnucmat.2008.04.016

[13] Komar Varela C, Mirandou M, Aricó S, Balart S, Gribaudo L. Interdiffusion between U(Mo, Pt) or U(Mo, Zr) and Al or Al A356 alloy. J Nucl Mater 2009; 395: 162.

DOI: 10.1016/j.jnucmat.2009.10.050

[14] Kim Y, Hofman G, Ryu H, Hayes S. Irradiation-enhanced interdiffusion in the diffusion zone of U-Mo dispersion fuel in Al. J Phase Equilib Diff 2006; 27: 614.

DOI: 10.1007/bf02736563

[15] Ryu H, Park J, Kim C, Kim Y, Hofman G. Diffusion reaction behaviors of U-Mo/Al dispersion fuel. J Phase Equilib Diff 2006; 27: 651.

DOI: 10.1007/bf02736568

[16] Massalski TB, editor Binary Phase Diagrams, 2nd Ed.: American Society for Metals, (1990).

[17] Davis JR, editor. ASM Handbook Volume 2: Properties and Selection: Nonferrous Alloys and Special-Purpose Materials, (1992).

[18] Wiencek TC, Prokofiev IG, McGann DJ. Development and compatibility of magnesium-matrix fuel plates clad with 6061 aluminum alloy. 1998 International Meeting on Reduced Enrichment for Research and Test Reactors. São Paulo, Brazil, (1998).

[19] Laxman, S, Franke, B, Kempshall BW, Sohn YH, Giannuzzi LA, Murphy KS. Phase transformations of thermally grown oxide on (Ni, Pt)Al bondcoat during electron beam physical vapor deposition and subsequent oxidation, Surf Coat Technol 2004; 177/8: 121.

DOI: 10.1016/j.surfcoat.2003.08.072

[20] Perez E, D. D. Keiser J, Yao B, Sohn YH. Interdiffusion in diffusion couples: U-Mo v. Al and Al-Si. 31st International meeting on RERTR. Beijing, China, (2009).

[21] Sears VF. Neutron scattering lengths and cross sections. Neutron News 1992; 3: 26.

DOI: 10.1080/10448639208218770