| 摘要 |
<p>1,021,413. Processing spent nuclear fuel. UNITED STATES ATOMIC ENERGY COMMISSION. Sept. 14, 1964 [Nov. 20, 1963], No. 37430/64. Heading G6R. Pyrolytic carbon cladding is removed from uranium nuclear fuel elements by treatment at or above 675‹ C. in a bed of aluminium oxide particles fluidized with an oxygen-containing gas; the uranium is then recovered by passing gas containing fluorine through the bed at 400‹ to 450‹ C. and collecting the uranium fluoride formed. The fuel may be uranium dicarbide microspheres coated with pyrolytic carbon and dispersed in a graphite matrix. The fluidizing gas may be air or pure oxygen, carbon being removed as CO or CO 2 .</p> |
