| 摘要 |
<p>A sintered UO2 nuclear fuel body is pulverized by oxidizing to U3O8 and then reducing back to UO2. Oxidation may be carried out with air or oxygen at 300 DEG -500 DEG C. and reduction by thermal decomposition under vacuum at 1100 DEG -1300 DEG C. or by treatment with hydrogen at 500 DEG -800 DEG C. The oxidation and reduction cycle may be repeated four to five times with progressive lowering of the temperature. When the fuel body has been used in a nuclear reactor, the treatment partly decontaminates the fuel from fission products; for this purpose an oxidation temperature of 600 DEG -1200 DEG C. in at least one cycle is preferred. Tables are given showing the degree of comminution and decontamination obtained by treating sintered UO2 pellets.</p> |
