Method for the manufacture of oxidic sintered nuclear fuel...

Details Method for the manufacture of oxidic sintered nuclear fuel... Method for the manufacture of oxidic sintered nuclear fuel...

G - Physics

21

C

31/89

G21C 3/62 (2006.01)

Patent

CA 1182994

ABSTRACT OF THE DISCLOSURE Method for the manufacture of oxidic nuclear fuel bodies by a heat treatment of blanks obtained from UO2 starting powder or a mixture of UO2 and PuO2 starting powder at a treatment tempera- ture in the range of 1000°C to 1400°C initially in a gas atmosphere with oxidizing action and subsequently in a gas atmosphere with reducing action. The oxygen potential of the gas atmosphere with oxidizing action is kept in a range in which a crystallographically demonstrable U4O9 or (U, Pu)4O9 crystal phase is generated in the blanks during the heating to the treatment temperature in this gas atmosphere with oxidizing action.

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