Skip to main content
Log in

Improvement in the Technology for Extracting U–9%Mo Granules from Aluminum and Aluminum Alloy Based Dispersion Compositions

  • Published:
Atomic Energy Aims and scope

A classification by form and fraction of production turnovers with U–9%Mo fuel is made. The technology developed at the Institute of Physics and Power Engineering allowing unconditioned fuel rods and recovered material to be dissolved in a 10% solution of sodium hydroxide at temperatures 75–100°C is examined. The process developed for the Novosibirsk Chemical Concentrates Plant for extracting U–9%Mo granules from recovered material obtained in the production of dispersion-type fuel rods of the experimental IRT-3M fuel assemblies is examined. The optimal regimes for extracting U–9%Mo granules during the processing of recovered material obtained in production of dispersion fuel rods are determined and perfected. The basic chemical reactions involved in the process of dissolution of the aluminum matrix are presented. The U–9%Mo granules, initial and recovered from the dispersion fuel composition of the kernels and fuel rods, were investigated, the possible differences between them were determined, and the possibility of using recovered granules in the production of dispersion fuel rods was evaluated.

This is a preview of subscription content, log in via an institution to check access.

Access this article

Price excludes VAT (USA)
Tax calculation will be finalised during checkout.

Instant access to the full article PDF.

Similar content being viewed by others

References

  1. J. Figueroa, M. Williamson, and G. Vandegrift, Pyrochemical Scrap Recovery in the Fabrication of Leu Monolithic U–Mo Fuel for High-Performance Research Reactors, Chem. Sci. Eng. Division, Argonne Nat. Lab., Argonne, IL, USA (2010).

  2. C. Dominique, K. Stepinski, L. Maggos, et al., Scrap Recovery Operations in the Fuel Fabrication Capacity, Chem. Sci. Eng. Division, Argonne Nat. Lab., Argonne, IL, USA (2008).

  3. A. T. Ageenkov, E. A. Nenarozhomov, V. F. Savel’ev, and A. B. Yastrebov, Preparation of Irradiated Nuclear Fuel for Chemical Reprocessing, Energoatomizdat, Moscow (1982).

    Google Scholar 

  4. S. Stoler and R. Richards, Reprocessing of Nuclear Fuel, Atomizdat, Moscow (1964).

    Google Scholar 

  5. R. Kh. Gibadulin, V. V. Popov, and V. M. Troyanov, “Technological research on the use of uranium-molybdenum fuel with reduced uranium enrichment for research reactors,” in: 7th Russ. Conf. on Reactor Materials Science, Dimitrovgrad, Sept. 8–12, 2003, Dimitrovgrad (2004), Vol. 2, pp. 104–118.

  6. G. Ya. Sergeev, V. V. Titova, and K. A. Borisov, Metallurgy of Uranium and Some Reactor Materials, Atomizdat, Moscow (1960).

  7. O. S. Ivanov, Phase Diagrams and Phase Transformations of Uranium Alloys, Nauka, Moscow (1972).

    Google Scholar 

  8. Specifications 336.072.00.000TU, Powder from a Uranium Alloy with 9 wt.% Molybdenum, VNIINM, Moscow (2005).

Download references

Author information

Authors and Affiliations

Authors

Corresponding author

Correspondence to I. V. Vasil’kov.

Additional information

Translated from Atomnaya Énergiya, Vol. 127, No. 8, pp. 76–81, August, 2019.

Rights and permissions

Reprints and permissions

About this article

Check for updates. Verify currency and authenticity via CrossMark

Cite this article

Vasil’kov, I.V., Shadrin, A.Y. Improvement in the Technology for Extracting U–9%Mo Granules from Aluminum and Aluminum Alloy Based Dispersion Compositions. At Energy 127, 87–92 (2019). https://doi.org/10.1007/s10512-019-00590-6

Download citation

  • Received:

  • Published:

  • Issue Date:

  • DOI: https://doi.org/10.1007/s10512-019-00590-6

Navigation