Branch Scientific-Research Laboratory 709, National Research Nuclear University “MEPhI” (Moscow Engineering Physics Institute), Moscow, Russia:

D. P. Shornikov, Senior Researcher, e-mail: d.p.shornikov@mail.ru
V. G. Baranov, Professor of a Chair “Physical Problems of Materials Science”, Manager
S. N. Nikitin, Engineer
B. A. Tarasov, Engineer

Fast reactors are the basis of world nuclear energy. Metal alloys U – Mo, U – Zr, (U, Pu) – Zr are offered as an advanced fuel for fast reactors. These alloys possess such advantages as high thermal conductivity, high density, simple manufacturing and reprocessing. The disadvantages of metal fuel include low melting point, interaction with stainless steel cladding (eutectic formation), radiation growth and gas swelling. This paper describes the main results of study of porous metal fuel based on uranium-molybdenum and uranium-zirconium alloys. This type of fuel will be innovative and will be used for fast breeder reactor. The methods of production of uranium alloy powders are considered, and pressing and sintering modes are described. The metal fuel powder with a particle size of 0.2–0.7 mm was obtained with following milling in a high energy ball mill to a size of 50–100 m, and annealing. Pressing was carried out at a pressure of 30–65 MPa, in which case, the relative density of the compact is 60–75% of TD, while sintering was carried out in the temperature range of 600–900 °C. This paper notes that density and porosity of fuel pellets depends on pressing pressure and sintering temperature. The main results of X-ray diffraction and EMPA metal fuel pellets are shown. Thee is considered the possibility of application of high voltage electro discharge consolidation for pressing fuel pellets.

1. Kazachkovskiy O. D. et al. The present status of the fast reactor programme in the USSR. Proceedings of International Conference on Nuclear Power and its Fuel Cycle. Salzburg, 1977. pp. 393–414.
2. Crawford D. C., Porter D. L., Hayes S. L. Fuels for sodium-cooled fast reactors: US perspective. Journal of Nuclear Materials. 2007. Vol. 371. pp. 202–231.
3. Stevenson C. E. The EBR-II Fuel Cycle Story. American Nuclear Society. 1987.
4. Tokita M. Development of advanced Spark Plasma Sintering (SPS) systems and its applications. Ceramic Transaction. 2006. Vol. 194. pp. 51–60.
5. Porter D. L., Chichester H. J. M., Medvedev P. G., Hayes S. L., Teague M. C. Performance of low smeared density sodium-cooled fast reactor metal fuel. Journal of Nuclear Materials. 2015. Vol. 465. pp. 464–470.
6. Wright A. E., Hayes S. L., Bauer T. H., Chichester H. J., Hofman G. L., Kennedy J. R., Kim T. K., Kim Y. S., Mariani R. D., Pointer W. D., Yacout A. M., Yun D. Development of advanced ultra-high burnup SFR metallic fuel concept — Project overview. Transactions of the American Nuclear Society. 2012. Vol. 106. pp. 1102–1105.

7. Status and Trends of Nuclear Fuels Technology for Sodium Cooled Fast Reactors. Vienna : IAEA Nuclear Energy Series, 2011. 113 p.
8. Baldev Raj, Kamath H. S., Natarajan R., Vasudeva Rao P. R. A Perspective on Fast Reactor Fuel Cycle in India. Progress in Nuclear Energy. 2005. Vol. 47. pp. 369–379.
9. Muralidaran P., Prabhu T. V., Manivannan A., Vinod A. V., Padmanabhan R., Ravisankar G., Ganesan V., Vasudeva Rao P. R. Fabrication experience of sodium bonded metallic test fuel pin with 6%Zr in T91 clad tube for irradiation in FBTR. Proceedings of International Conference CQCNF. Hyderabad, India. 2012.
10. Nagarajan K., Vaidya V. N. Sol-Gel processes for nuclear fuel fabrication. Sol-Gel Processing for Conventional and Alternative Energy. New York : Springer, 2012. pp. 341–373.
11. Prabhu T. V., Venkata Krishnan R., Padmanabhan R., Brij Mohan Singh, Kothandaraman B., Senapathy A., Jogeswara Rao G., Nagarajan K., Ravisankar G. A Remotely Operable Facility for Fabrication of Fuel Pins for test Irradiation. Proceedings of Asian Nuclear Prospects. 2010. Vol. 7. pp. 222–226.
12. Venkata Krishnan R., Nagarajan K., Clement Ravichandar S., Prabhu T. V., Ravisankar G., Kasiviswanathan K. V. Sol-Gel development activities at IGCAR. Journal of Sol-Gel Science and Technology. 2011. Vol. 9. pp. 394–403.
13. Jia J.-P, Wang Z.-G., Chen M., Wang X.-S., Zhang P.-C., Wu S. Preparation of Porous U–10%Mo alloy by Powder Metallurgy and Its Microstructure Characterization. Atomic energy Science and Technology. 2013. Vol. 47. pp. 295–298.