| 摘要 |
<p>972, 663. Recovery of plutonium. UNITED STATES ATOMIC ENERGY COMMISSION. April 18, 1963 [July 25,1962], No.15293/63. Heading G6R. In recovering plutonium from a chlorinatable nuclear fuel, a mixture comprising lithium chloride, or a salt selected from CaCl 2 , BaCl 2 , SrCl 2 and MgCl 2 , an approximately equimolar alkalimetal-aluminium double chloride, the said fuel and aluminium is maintained above melting temperature, agitated to ensure reaction, allowed to separate into three phases, and the plutonium containing phase removed therefrom. The nuclear fuel may, for example, be a plutonium aluminium alloy, in which case the addition of aluminium to the reaction mass is unnecessary, or a plutonium oxide, -uranium oxide ceramic material. The alkali-metal-aluminium double chloride is preferably potassium aluminium chloride. The temperature of the reaction is maintained between 700 and 800‹C. and the mass is then cooled to 600‹C. before phase separation. The three phases obtained are a heavy aluminium phase, an intermediate salt extractant phase containing the Pu and a light phase of double chloride. Further processing by a standard salt cycle process (Specification 945,899) extracts the plutonium from the intermediate phase. Specification 945,899 is referred to.</p> |
