| 摘要 |
<p>1,064,224. Fuel materials. COMMISSARIAT A L'ENERGIE ATOMIQUE. Oct. 29, 1964 [Nov. 5, 1963], No. 44229/64. Heading G6C. Nuclear fuel material, for use especially in breeder reactors, consisting of a mixture of UC and PuN is prepared by mixing PuN with C -and UH 3 in suitable respective proportions, heating the mixture to form UC and sintering the resulting mixture of UC and PuN under a pressure in the range of 2,000 to 15,000 bars at a temperature in the range of 1200‹ to 1700‹ C. The preparation of the fuel may be carried out in a single operation, after the incorporation of 1% by wt. of naphthalene as binder and 0À5% by wt. of nickel as sintering adjuvant, at a temperature within the range of 1200‹ to 1700‹ C., at a pressure in the range of 2,000 to 10,000 bars and for between 2 and 6 hours. Alternatively, the ingredients in powder form are compacted to form pellets under a pressure in the range of 2,000 to 10,000 bars, which pellets are homogenized by heating in vacuo at a temperature in the range 1200‹ to 1500‹ C. for between 2 and 6 hours and then ground, the resulting powder having added to it 1% by wt. of naphthalene and 0À5% by wt. of nickel and then being compacted to form pellets under a pressure in the range of 8,000 to 15,000 bars, which pellets are sintered by heating at a temperature in the range of 1200‹ to 1500‹ C. under a pressure in the range of 10<SP>-5</SP> to 10<SP>-6</SP> mm .of Hg for between 2 and 6 hours. The sintered pellets may be subjected to an annealing treatment by heating at 1600‹ C. for between 2 and 6 hours. Fuel materials made by the first of the above methods have a density of 11À8 to 12À2 gm/cc. and those made by the second method a density of 12À4 and 13À0 gm/cc. In the fabrication of breeder reactor fuel elements, the weight percentage of PuN is advantageously within the range 2 to 25%.</p> |
