Dispersion type zirconium matrix fuels fabricated by capillary impregnation method

New concept of designing Pu and MA containing fuel for fast reactors

“…The major drawback of dispersion fuel, viz., its low uranium content in this design is compensated for the applied high density uranium metal fuel and compatible with it zirconium alloy matrices [3,4].…”

“…In the suggested design metal fuel of U-Mo, U-Zr and U-Zr-Nb alloys forms a porous frame bonded by a zirconium matrix alloy; the pores of the frame contain PuO 2 powder manufactured by pyrochemical or other methods [3,4]. The fuel meat metallurgically bonded to a cladding promotes the high thermal conductivity to mixed U-PuO 2 fuel, while the Zr-base matrix alloy improves the compatibility between fuel components.…”

“…Zirconium eutectic alloys are used as matrices [4,5]. The sizes of the matrix granules are 0.1-0.3 mm.…”

“…Granules of fuel (U-Mo, U-Zr or U-Zr-Nb alloys) of depleted uranium and of a matrix are loaded into a fuel element cladding and the fuel element is heated to a temperature 50°C higher than the melting temperature of a matrix ( Fig. 3(a) and (b)) [3][4][5].…”

Physical Metallurgical Studies of Zr-Rich U-Zr Alloys

“…Uranium-zirconium alloys are main constituents for making metallic fuels. These fuels find their use in monolithic form for fast reactor and in dispersion form in thermal reactor [2,3]. With suitable enrichment of uranium, zirconium rich U-Zr alloys could be used as dispersion fuel in advanced pressurized water reactor.…”