| 摘要 |
<p>PROBLEM TO BE SOLVED: To simplify reprocessing process and improve the recovery of actinoid elements by dissolving spent nitride nuclear fuel in molten salt and adding lithium nitride in the molten salt. SOLUTION: In an anode basket 2 in molten salt phase 3 of LiCl-KCl-CdCl2 , a sintered body 1 of mixed nitride of uranium-cerium-neodymium-zirconium is loaded and dissolved in the molten salt phase 3. As a result, uranium, cerium, neodymium in the nitride dissolves and undissolved zirconium is separated as an undissolved component. Nitrogen discharged during dissolution is introduced to metal lithium 6P to produce lithium nitride 7. This lithium 7 is added into the molten salt phase 3 to deposit only uranium nitride 8. The deposited uranium nitride 8 is precipitated on liquid cadmium 4 at the bottom of the molten salt phase 3 to separate and recover. By heating this and evaporating and removing liquid cadmium 4, the recovery of actinoid elements such as uranium is improved and the reprocessing process can be simplified.</p> |
