1) simulated high lever radioactive waste
模拟高放射性废液
1.
The exchange capacity of Cs+ in simulated high lever radioactive waste and the leaching rate of Cs+ in solidified alkali-activated slag cement were investigated when NiSO4 and K4 [Fe(CN)6 ] were added to the waste in different pretreatment processes.
研究了模拟高放射性废液在不同的预处理工艺条件下,加入NiSO4和K4[Fe(CN)6]后,碱矿渣水泥固化其废液中Cs+的作用机理。
2) simulated HLLW
模拟高放废液
1.
Zirconium is adsorbed and separated by high adsorption activity silica gel in simulated HLLW.
用自制高吸附活性硅胶吸附分离模拟高放废液中的锆 ,并对吸附机理进行了分析。
3) simulated high level liquid waste
模拟高放废液
1.
Based on the single stage extraction experiments of rare earth elements with 22 % DHDECMP 42 % TBP/OK, the extraction behavior of the rare earth elements in simulated high level liquid waste are determined on miniature countercurrent centrifugal contactor cascade (6 stages for extraction, 2 stages for scrubbing, 6 stages for stripping, AF∶AX∶AS=1∶1.
测定了用 2 2 %DHDECMP 4 2 %TBP/OK从模拟高放废液中萃取各稀土元素的分配比。
2.
On the basis of tuble tests, courtcurrent experiments with miniature mix settler is carried out to separate U(Ⅵ),Pu(Ⅳ),Am(Ⅲ) and Eu(Ⅲ) from simulated high level liquid waste solution by the extractant of 0.
用 0 0 75mol/LTBOPDA +0 5mol/LN 50 3/ 4 0 %辛醇 煤油为萃取剂 ,从模拟高放废液中分离U(Ⅵ )、Pu(Ⅳ )、Am(Ⅲ )和Eu(Ⅲ )的微型混合澄清槽实验结果表明 :在A槽 ,大于 99 99%的U(Ⅵ )、Pu(Ⅳ )、Eu(Ⅲ )和Am(Ⅲ )被萃入有机相 ;在R1槽 ,U(Ⅵ )被定量反萃 ,83 %的Pu(Ⅳ )和 36%的Am(Ⅲ )被反萃入水相 ;在R2槽中残留的Pu(Ⅳ )、Am(Ⅲ )和Eu(Ⅲ )可被定量反萃下来。
3.
The dynamic adsorption behavior of Zr on silica xerogel with a size of nano meter and the selective adsorption of Zr from simulated high level liquid waste are studied experimentally.
研究了模拟高放废液中的锆在成型后的SiO2 纳米干凝胶上的动态吸附行为。
4) highly active waste
高放射性废液
1.
Trialkylphosphine oxide extraction- An effective process for the recovery of actinides from highly active waste solution;
三烷基氧膦革取──由高放射性废液回收锕系元素的有效方法
5) simulated waste liquid
模拟高碱高放废液
6) simulated radioactive spent resins
模拟放射性废树脂
补充资料：高放射性水平废液
分子式：
CAS号：
性质：比活度大于3.7×109Bq/L的放射性废液。主要是乏燃料后处理厂的共去污循环工段的萃余水相(即1AW废液)，几乎含有乏燃料中的全部裂变产物(大于99.9％)，其特点是放射性含量.高，释热量大，在放射性废物管理中占有重要位置，在贮存、处理和运输过程中需要特殊的防护，必须进行固化及最终处置。
CAS号：
性质：比活度大于3.7×109Bq/L的放射性废液。主要是乏燃料后处理厂的共去污循环工段的萃余水相(即1AW废液)，几乎含有乏燃料中的全部裂变产物(大于99.9％)，其特点是放射性含量.高，释热量大，在放射性废物管理中占有重要位置，在贮存、处理和运输过程中需要特殊的防护，必须进行固化及最终处置。
说明：补充资料仅用于学习参考，请勿用于其它任何用途。
参考词条