1) 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。
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 waste liquid
模拟高碱高放废液
4) 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。
5) High level liquid waste
高放废液
1.
Determination of Free Acid in High Level Liquid Waste(In Chinese);
高放废液中游离酸的测定
2.
A description and review on the techniques of avoiding second organic phase in the treatment of high level liquid waste (HLLW) by solvent extraction is presented.
概要介绍和评述了用溶剂萃取法处理高放废液时避免产生第二有机相的若干技术 :复合萃取体系、芳香烃作为稀释剂、稀释法、还原法、络合法以及非平衡萃取法。
3.
A description and review of the stripping agent used in solvent extraction process for treatment of high level liquid waste are presented.
简要评述了国内外处理高放废液的萃取流程中所采用的反萃剂。
6) high level radioactive liquid waste
高放废液
1.
In the simulated high level radioactive liquid waste (HLLW) system, the results of the selective test show that if the V∶m is suitable, the effect of rare earth elements o.
对比了提铯离子筛对铯离子与部分稀土元素的交换容量和分配系数 ;研究了钕离子对提铯离子筛铯离子交换性能的影响 ,以及稀土元素存在对提铯离子筛在高放废液中选择性的影响。
2.
The adsorption and elution of metal elements included in high level radioactive liquid waste on PAIV levextrel chromatographic column were investagated.
研究了高放废液中金属元素在 PAIV(酰胺荚醚 )萃淋树脂色层柱上的吸附及淋洗性能。
补充资料：高放废液固化
分子式：
CAS号：
性质：使高放废液转化为固化体的处理过程。目的是减小放射性物质向自然环境释放、扩散和迁移的能力。高放废液的固化方法有:煅烧法、玻璃固化法、陶瓷固化法、复合固化法。目前普遍认为，将高放废液固化再进行最终处置是处理高放废液安全而可行的方法。
CAS号：
性质：使高放废液转化为固化体的处理过程。目的是减小放射性物质向自然环境释放、扩散和迁移的能力。高放废液的固化方法有:煅烧法、玻璃固化法、陶瓷固化法、复合固化法。目前普遍认为，将高放废液固化再进行最终处置是处理高放废液安全而可行的方法。
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