从核燃料后处理废液中提取锝(Ⅱ)——锝与裂片元素的分离

RECOVERY OF TECHNETIUM FROM SPENT NUCLEAR FUEL-PROCESSING WASTE SOLUTION (PART Ⅱ)……THE SEPARATION OF TECHNETIUM FROM OTHER FISSION PRODUCTS

本文为从核燃料后处理废液中提取锝研究的第二部分。以萃取法为基本方法从甲酸脱硝后的沉淀中提取锝。产品锝的回收率在90％以上,对一些主要长寿命放射性核素的去污系数分别为:^(144)Ce/^(144)Pr>6.1×10~4,^(125)Sb>6.3×10^(5.93)Zr>2.5×10~3,^(100)Ru/^(106)Rh>1.2×10~6,^(103)Rh>2.8×10~4,^(100)Mo等>5.4×10~3,(107)Pd等>1.5×10~5。

This work is the second part of the recovery of technetium from a simulated spent nuclear fuel-processing waste solution.Solvent extraction was used as a main method to recover technetium from the precipitation obtained from denitration with formic acid.The technetium of recovery exceeded 90%has been produced and the decontamination factors to some main long-life radionuclides are ^(144)Ce/^(144)Pr>6.1×10~4, ^(125)Sb>6.3×10~5, ^(93)Zr>2.5×10~3, ^(106)Ru/^(106)Rh >1.2×10~6 ^(103)Rh>2.8×10~4, ^(100)Mo etc·>5.4×10~3, and ^(107)Pd etc·>1.5× 10~5 respectively.