CAJ | 학술논문

本文建立了有效、定量分离后处理铀产品中镎的方法。该方法采用 TEVA-UTEVA萃取色层分离后处理铀产品中的微量镎，先将镎调至四价后过 TEVA 萃取色层柱，再用2 mol/L HNO3-0.2 mol/L H2C2O4解吸吸附在TEVA树脂上的镎，最后将镎解吸液稀释后过 UTEVA萃取色层柱进一步分离。结果表明，镎的平均全程回收率约为94％，铀的去污因子＞104。
본문건립료유효、정량분리후처리유산품중나적방법。해방법채용 TEVA-UTEVA췌취색층분리후처리유산품중적미량나，선장나조지사개후과 TEVA 췌취색층주，재용2 mol/L HNO3-0.2 mol/L H2C2O4해흡흡부재TEVA수지상적나，최후장나해흡액희석후과 UTEVA췌취색층주진일보분리。결과표명，나적평균전정회수솔약위94％，유적거오인자＞104。
An efficient and quantitative extraction chromatographic method using commercially available TEVA resin and UTEVA resin was developed for the separation of neptunium from reprocessed uranium .Before the sample was loaded onto TEVA column ,neptunium was adjusted to Np (Ⅳ ) ,and then the eluent of 2 mol/L HNO3-0.2 mol/L H2 C2 O4 was loaded to elute the neptunium ,the uranium in eluent after diluting was retained on UTEVA resin ,while Np(Ⅳ) was stripped from the resin .The average recovery of neptunium of the w hole separation procedure is about 94% and the decontamination coefficient of uranium is more than 104 .