Rapid separation of uranium and plutonium by extraction chromatography for determination by thermal ionisation mass spectrometry
Rapid separation of uranium and plutonium by extraction chromatography for determination by thermal ionisation mass spectrometry
复制标题
萃取色谱法快速分离铀和钚并用热电离质谱法测定
作者：
P. Goodall;C. Lythgoe
开发了一种基于萃取色谱的快速方法，用于从乏核燃料溶液中分离 U 和 Pu，用于热电离质谱分析。该方法涉及将 Pu(IV) 和 U(VI) 保留在 UTEVA 柱上，从而实现这些锕系元素与裂变产物的分离。然后通过选择性洗脱 Pu 实现 Pu 与 U 的分离。研究了实现这种选择性洗脱的两种方法：(a) 使用草酸竞争性络合和 (b) 使用抗坏血酸将 Pu(IV) 还原为 Pu(III)。后一种方法产生了更纯的分离物，因为前一种方法产生的 Pu 分离物受到了不可接受的量的 U 污染。UTEVA 分离速度比现有分离速度快 3-5 倍，被认为更适合自动化。
A rapid method based upon extraction chromatography was developed for the separation of U and Pu from solutions of spent nuclear fuel for thermal ionization mass spectrometry. The method involves retention of Pu(IV) and U(VI) on a UTEVA column, thereby accomplishing a separation of these actinides from fission products. A separation of Pu from U was then achieved by selective elution of Pu. Two approaches for accomplishing this selective elution were investigated: (a) competitive complexation using oxalic acid and (b) reduction of Pu(IV) to Pu(III) using ascorbic acid. The latter method yielded a purer isolate as the former method yielded a Pu isolate that was contaminated with an unacceptable amount of U. The UTEVA separation was 3–5 times more rapid than the existing separation and was considered to be more suitable for automation.