1) Management of high radioactive liquid waste
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高放废液管理
2) High level liquid waste
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高放废液
1.
Determination of Free Acid in High Level Liquid Waste(In Chinese);
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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。
3) high level radioactive liquid waste
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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。
4) HLLW
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高放废液
1.
Activity Determination of ~(89,90) Sr in HLLW by TIBOGA Extraction-liquid Scintillation Counting Method;
TIBOGA萃取液闪法测定高放废液中的~(89,90)Sr
2.
A DETERMINATION METHOD OF Ru, Rh AND Pd IN HIGH-LEVEL LIQUID WASTE(HLLW) BY CATIONEXCHANGE SEPARATION AND ICP-AES MEASUREMENT;
阳离子交换分离ICP-AES法测定高放废液中微量钌、铑、钯
3.
A typical simulated high level radioactive sludge is prepared according to the analysis data of high level liquid waste (HLLW) and sludge.
依据高放废液化学组分分析结果 ,配制了模拟高放废液。
5) HLW
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高放废液
1.
By comparing glass and mineral hosts for HLW, author discussed their properties.
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对高放废液玻璃固化体和矿物固化体的性能作了比较和分析。
6) α-HLLW
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α-高放废液
1.
Study on Monazite Phosphate Glass-ceramics as Wasteform for Simulated α-HLLW;
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模拟α-高放废液独居石磷酸盐玻璃陶瓷固化体的研究
补充资料:高放废液
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