| 摘要 |
<p>1,206,776. Uranium recovery. GENERAL ELECTRIC CO. 8 Nov., 1967 [17 Nov., 1966], No. 50767/67. Heading C1A. [Also in Division G6] In order to recover uranium and transuranic material from irradiated nuclear fuel, the fuel is dissolved in strong mineral acid, uranium and transuranic material are extracted with an organic solvent, fission products are recovered from the aqueous phase, uranium and transuranic material are transferred to an aqueous phase, this aqueous phase is contacted with anion exchange resin to remove transuranic material which is eluted from the resin, and the aqueous resin saffinate is dehydrated, the solids calcined to uranium oxide, and the oxide fluorinated to UF 6 . The process described is similar to that of Specification 1,206,775 (see Division G6), except that the neptunium extraction step may be omitted. Extraction of the orginal fuel solution with tributyl phosphate in dodecane is described in more detail; zinc nitrate, aluminium nitrate, alkali metal or alkaline earth metal borates, phosphates, or silicates may be added as diluents to the aqueous solution of fission products before evaporation and calcination. Further details and also given of the preparation and purification of UF 6 from the solution after removal of plutonium.</p> |
