| 摘要 |
<p>PROBLEM TO BE SOLVED: To improve the recovery rate of U3 O8 with the grain diameter of size not larger than the mesh so as not to cause defectiveness in the metal phase of pellet in manufacturing nuclear fuel pellet by adding scraps UO2 powder after oxidation recovery in a method of oxidizing to recover power, molding and sintered body scraps produced in manufacturing nuclear fuel pellet of UO2 or UO2 containing Gd2 O3 , as U3 O8 powder in an air atmosphere. SOLUTION: In this oxidation recovery method for nuclear fuel uranium scrap, scraps produced in manufacturing nuclear fuel pellet of UO2 or UO2 containing Gd2 O3 , are heated in air and oxidized to obtain U3 O8 . In this case, the sintered body scraps are mixed in both or one of powder scrap and molding scrap and simultaneously oxidized.</p> |
