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radiochemical
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  radiochemical
Functional activity of blood cells in fish exposed to radiochemical industrial sewage
      
The effect of the gas components of the working medium, which develops during the reprocessing of waste nuclear fuel at radiochemical plants, on the 129I fluorescence excited by radiation of He-Ne laser (633 nm) is studied.
      
The results were compared to the data obtained using radiochemical separation.
      
This instrument can measure 241Am activity in samples, without their concentration and radiochemical treatment, against a high (~10-3) background level due to the accompanying radionuclides (134Cs, 137Cs, 154Eu, 155Eu, etc).
      
A Radiochemical Installation for Handling Small Amounts of High-Purity Gases
      
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The amount of the residual plutonium-239 in the nuclear explosion debris was determined by mass-spectrometric and alpha-spectrometric analyses. The error caused by the influence of neptunium-239 on the determination of plutonium-239 was corrected by di-:rect subtraction or linear extrapolation. A radiochemical analytical procedure was proposed and a method for storing the plutonium isotopic diluent of very low concentration (10-9M) was recommended. An error less than±5% could be obtained for the direct...

The amount of the residual plutonium-239 in the nuclear explosion debris was determined by mass-spectrometric and alpha-spectrometric analyses. The error caused by the influence of neptunium-239 on the determination of plutonium-239 was corrected by di-:rect subtraction or linear extrapolation. A radiochemical analytical procedure was proposed and a method for storing the plutonium isotopic diluent of very low concentration (10-9M) was recommended. An error less than±5% could be obtained for the direct subtraction method which is applicable only when the total yield of uranium-239 is small, and when using this method, the uranium and neptunium must be separated from plutonium as early as possible. The error of the linear extrapolation is generally less than±4%, and this method is superior to the former one when the total yield of uranium-239 is large.

用质谱和α谱分析法测定了核爆炸烟云中的剩余钚-239量(~(239)Pu_R)。由~(238)U的(n,γ)反应并经级联β衰变而产生的~(239)Pu的干扰,通过直接扣除或线性拟合法予以校正。制定了适合测试要求的放化分析程序,并对低浓度(~10~(-9)M)的钚稀释剂溶液的贮存方法作了探讨。直接扣除法的误差不大于±5%,但仅适用于~(239)U产生量较少的情况,且应尽早地进行铀、镎、钚的定量分离。线性拟合法的误差一般小于±4%,对于~(239)U产生量较多的情况显得优越。

A method was established for simultaneous extracting and determining trace amountfof ~(95)Zr-~(95)Nb with tri-aliphatic amine(TAA) in ground water, containing long lived fission products. The method proves to be simple and rapid and has good reproducibility. This method in comparison with the extraction of ~(95)Zr~(95)Nb with TOA (trioctylamine), yields approximate same recoveries for ~(95)Zr-~(95)Nb and gives better decontamination factors for diverse radionuclides. Therefore, TAA is a new reagent worthy of...

A method was established for simultaneous extracting and determining trace amountfof ~(95)Zr-~(95)Nb with tri-aliphatic amine(TAA) in ground water, containing long lived fission products. The method proves to be simple and rapid and has good reproducibility. This method in comparison with the extraction of ~(95)Zr~(95)Nb with TOA (trioctylamine), yields approximate same recoveries for ~(95)Zr-~(95)Nb and gives better decontamination factors for diverse radionuclides. Therefore, TAA is a new reagent worthy of further attention in the field of radiochemical analysis.

本文建立了一个用三脂肪胺(TAA)从加有重要的长寿命裂变产物的地下水样中同时萃取和测定示踪量~(95)Zr-~(95)Nb的方法,该法简便、快速、重现性好、并比较了用TAA萃取剂与TOA(三辛胺)萃取~(95)Zr-~(95)Nb的试验,两者对~(95)Zr-~(95)Nb的回收率相似,但TAA对干扰核素的去污因素优于TOA,因此,TAA在放化分析的研究和应用中是一种值得注意的新试剂。

The tissue samples obtained at autopsy from corpse of a deadwho contacted with insoluble~(230)PuO_2 during his living time were analyzedwith radiochemical method for determining~(230)Pu content in tissues.It was fou-nd that there was~(230)Pu in some tissues,and the body burden(except lungs)of~(230)Pu was estimated to be 7.7×10~(15)μCi which is 0.2% of the maximumpermissible body burden and in the lungs to be 1.3×10~(-3)μCi which is 8.2%of the maximum permissibie lung burden.The results show that~(230)Pu...

The tissue samples obtained at autopsy from corpse of a deadwho contacted with insoluble~(230)PuO_2 during his living time were analyzedwith radiochemical method for determining~(230)Pu content in tissues.It was fou-nd that there was~(230)Pu in some tissues,and the body burden(except lungs)of~(230)Pu was estimated to be 7.7×10~(15)μCi which is 0.2% of the maximumpermissible body burden and in the lungs to be 1.3×10~(-3)μCi which is 8.2%of the maximum permissibie lung burden.The results show that~(230)Pu contentin hilum-lymph nodes is the highest,then in pneumo-lymph nodes,lungsand liver in decreasing order,but in others,such as kidney,spleen,muscleand bone it is a little higher than background of reagents.By inference fromthe distribution of~(230)Pu in tissues,the deposition of~(230)Pu in this case resul-ted from inhalation of insoluble plutonium.

对一例生前接触过难溶性 PuO_2的死者,用放化分析方法测定了其尸解组织中的~(239)Pu。结果发现其体内一些组织中有钚存在,由尸解组织分析估算的体内积存量(除肺组织外)为0.000077微居里,约为全身最大容许积存量的0.2%。肺组织积存量为0.0013微居里,为肺组织最大容许积存量的8.2%。测定结果还发现组织中钚的分布是,肺门淋巴结浓度最高,其后依次为肺淋巴结、肺、肝、而其余组织如肾、脾、肌肉、骨等则稍高于试剂本底值;支气管淋巴结因故未测。根据这种分布推测,体内钚的沉积来自难溶性钚的吸入。

 
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