Preparation of Uranium Nitride from Uranium Metal through by Hydriding and Nitriding Process

Abstract:

The RERTR Program (Reduced Enrichment in Research and Test Reactors) is an attempt to utilize uranium fuel enriched below 20% for nuclear research reactors. Since the program was launched by the United States in 1978, the International Atomic Energy Agency (IAEA) has recommended that UxSiy alloys, particularly U₃Si₂ and U₃Si compounds, be used to fuel nuclear research reactors with uranium loading rate up to 4.8 gU/cm³. Unfortunately, there are difficulties in reprocessing U₃Si₂ and U₃Si compounds due to the Si content. To overcome this problem, the IAEA initiated international cooperation to find the best solution in the development of new nuclear fuels to substitute the UxSiy alloys. In order to synthesize nuclear fuel containing high loading of uranium, research in developing uranium nitride (UN) from uranium metal has been conducted by reacting the massive uranium metal with hydrogen gas at a temperature of 573 K followed by dehydriding at a temperature of 773 K under vacuum pressure and nitriding at a temperature of 1073 K by introducing nitrogen gas in the reaction chamber. The X-ray diffraction analysis results showed that the hydriding process caused the uranium metal to turn into a stable compound, UH₃, which was identified by the changes of the massive shapes into fine metal powders. Dehydriding process at a temperature of 773 K caused the UH₃ compound to decompose into U metal powders, and when the metal powders were reacted with N₂ gas at 1073 K a stable phase identified as UN was formed. The results showed that it is possible to produce UN powders by hydriding, dehydriding, and nitriding process, although special handling of UH₃ and UN powders is required due to their pyrophoric nature.

• Periodical: Advanced Materials Research (Volume 789)
• Pages: 360-366
• DOI: https://doi.org/10.4028/www.scientific.net/AMR.789.360
• Online since: September 2013
• Authors: Hadi Suwarno
• Keywords: Dehydriding, Gas Nitriding, Hydriding, UH₃, UN

References

[1] J.L. Snelgrove, G.L. Hofman, M.K. Meyer, C.L. Trybus, T.C. Wiencek, Nucl. Eng. Des., Vol. 178 (1997), p.119.

[2] C.K. Kim, K.H. Kim, J.M. Park, D.B. Lee, S.J. Oh, K.H. Lee, H.T. Chae, D.S. Sohn, Progress of U-Mo Dispersion rod fuel qualification program in Korea, RERTR Meeting, Bariloche, Argentina, November 3-8, (2002).

[3] G.L. Hofman, Y.S. Kim, M.R. Finlay, J.L. Snelgrove, Recent observation at the post irradiation examination of low enriched U-Mo miniplates irradiated to high burnup, RERTR Meeting, Chicago, October 5-10, (2003).

[4] G.L. Hofman, M.R. Finlay, Y.S. Kim, Post-irradiation analysis of low enriches U-Mo/Al dispersions fuel miniplate tests, RERTR Meeting, Vienna, Austria, November 7-12, (2004).

[5] A. Leenaers, S. Van den Berghe, E. Koonean, C. Jarousse, F. Huet, M. Trotabas, M. Boyard, S. Guillot, L. Sannen, M. Verwerft, J. Nucl. Mat., Vol. 335 (2004), p.39.

DOI: 10.1016/j.jnucmat.2004.07.004

[6] Y.S. Kim, G.L. Hofman, H.J. Ryu, J. Rest, Thermodynamic and metallurgical considerations to stabilizing the interaction layers of U-MO/AL dispersion fuel, RERTR Meeting, Boston, MA, USA, November 6-10, (2005).

[7] A. Leenaers, S. Van den Berghe, E. Koonean, P. Jacquet, C. Jarousse, B. Guigon, A. Ballagny, L. Sannen, J. Nuc. Mat., Vol. 327 (2004), p.121.

DOI: 10.1016/j.jnucmat.2004.01.025

[8] P. E. Evans and T. J. Davies, J. Nucl. Mat., Vol. 10 (1963), p.43.

[9] P.D. Takkunen, Fabrication of Cermet of Uranium Nitrides and Tungsten or Molybdenum from Mixed Powders and From Coated Particles, NASA Technical Note, TN – D-5136.

[10] T. Kawakita, K. Ikeda, S. Moro, M. Saito, H. Sekimoto, Feasibility study on nitride fuel core and recycling system toward self-consistent nuclear energy system, Progress in Nuclear Energy, Vol. 40 (2002), p.597.

DOI: 10.1016/s0149-1970(02)00055-0

[11] R. Thetford and M. Mignanelli, Journal of Nuclear Materials, Vol. 320 (2003), p.44.

[12] F. Izumi, A Rietveld-Refinement Program RIETAN-94 for Angle-Dispersive X-Ray and Neutron Powder Diffraction, Nat'l., Inst. for Res. in Inorg. Matls., 1-1 Namiki, Tsukuba, Ibaraki 305, Japan, Revised on June 22, (1996).

[13] T.B. Massalski, Binary Alloys Phase Diagrams, 2nd Edition, Vol 3, pp.2070-2072, (1990).

[14] H. E. Flotow and B. M. Abraham, US Atomic Energy Commission Publication, AECD-3074 (1951).

[15] E.H. P Cordfunke, The chemistry of uranium including its applications in nuclear technology, Elsevier Pub. Coy., pp.59-62, (1969).

[16] G.G. Libowitz, J. Nucl. Mat., Vol. 2 (1960), p.1.

[17] T. Yamamoto, S. Tanaka, M. Yamawaki, J. Nuc. Mat., Vol. 170 (1990), p.140.

[18] F. L. Guyadec, X. Genin, J.P. Bayle, O. Dugne, A.D. Barone, C. Ablitzer, J. Nuc. Mat., Vol. 396 (2010), p.294.

[19] T.B. Massalski, Binary Alloys Phase Diagrams, 2nd Edition, Vol 3, pp.2709-2710, (1990).

[20] Anonymous, IAEA, Development Status of Metallic, Dispersion and Non-Oxide Advanced and Alternative Fuels for Power and Research Reactors, IAEA-TECDOC-1374, (2003).

[21] K. Kurosaki, K. Yano, K. Yamada, M. Uno, S. Yamanaka, J. Alloys Comp., Vol. 319 (2001), p.253.

[22] Y. Arai, A. Maeda, K. Shiozawa, T. Ohmichi, J. Nuc. Mat., Vol. 210 (1994), p.161.

[23] S.L. Hayes, J.K. Thomas, K.L. Peddicord, J. Nuc. Mat., Vol. 171 (1990), p.271.

[24] S.L. Hayes, J.K. Thomas, K.L. Peddicord, J. Nuc. Mat., Vol. 171, (1990), p.300.

[25] V.G. Baranov, Yu.N. Devyatko, A.V. Tenishev, A.V. Khlunov, O.V. Khomyakov, J. Nuc. Mat., Vol. 434 (2013), p.248.

DOI: 10.1016/j.jnucmat.2012.10.047