| 摘要 |
<p>1. A process for the manufacture of mixed oxide nuclear fuel pellets which are soluble in nitric acid and consist of uranium dioxide (UO2+x ) and plutonium dioxide (PuO2 ), by grinding the powder mixture with a PUO2 -content of up to 50 % in mills inside glove boxes and subsequent granulating, pressing and sintering, characterized in that prior to grinding, the starting material is supplied with water, polyalcohols, preferably propanediol, fatty acids, or amines, as halogen-free auxiliary grinding agents which can be expelled by subsequent drying steps or heat treatments (sintering), and the grinding step is controlled in such a way that a primary grain size of less than 2 micrometres is obtained.</p> |
