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    PERMEABILITY OF HYDROGEN THROUGH RIT STAINLESS STEEL, Nb-1%Zr ALLOY AND 69-1~# ENEMAL The problem of hydrogen permeating through the cladding of zirconium hydride nuclear element
    氢气对不锈钢、铌-1%合金和搪瓷的渗透——氢化元件包壳的氢渗透问题
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    STUDY ON THE COEXTRACTION BEHAVIOUR OF Zr(Ⅳ) AND TcO_4~- IN HNO_3-30% TBP/OK SYSTEM
    HNO_3-TBP/OK体系中、锝共萃取行为的研究
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    Simulations of Bulk Effects of Zr on Cohesion of Ni_3Al Grain Boundary
    模拟(Zr)的基体效应对Ni_3Al-x atoms % Zr晶界内聚性的影响(英文)
    As moderator, Zirconium hydride works at temperature between 650℃ and 750℃ in space piles, in this case, zirconium hydride (atom ratio of H/Zr >1.8) loses its hydrogen easily.
    作为中子慢化剂,氢化的工作温度为650~750℃,在此温度下,H/Zr原子比大于1.8的氢化的分解压远远高于一个大气压,氢化中的氢将很容易析出。 氢的析出一方面增大了包壳中的压力;
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    The effect of aluminum tube is the most remarkable, it results in Ar8+ ions beam intensity rising from 245 μA to 330 μA, Ar9+ ions from 125 μA to 150 μA in comparison to Zr tube.
    铝筒的增强效果最为显著。 与简相比,Ar(8+)离子的束流强度从245μA增至330μA,Ar(9+)离子从125μA增至150μA。
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    Measurement of small-angle elastic scattering of fast neutrons from Zr and Nb nuclei
    快中子在Zr对Nb核上的小角弹性散射角分布测量
短句来源
    HOMOGENEITY KANGE AND STRUCTURE OF δ PHASE IN U-10Zr ALLOYS
    U-10Zr合金δ相的均匀范围和结构
短句来源
    Determination of the D-T neutron Energy by the Cross Section Ratio of ̄( 90)Zr(n, 2n) ̄( 89m+g)Zr to ̄(93)Nb (n,2n) ̄(92m)Nb Reactions
    用~(90)Zr(n,2n)~(89m+g)Zr和~(93)Nb(n,2n)~(
短句来源
    The Measurement of Cross Sections for 90 Zr(n,2n) 89 Zr Recation
    ~(90)Zr(n,2n)~(89)Zr反应截面测量
短句来源
    Corrosion Behavior of Zr(Fe,Cr)2 MetallicCompounds in 500℃ Superheated Steam
    Zr(Fe,Cr)_2金属间化合物在500℃过热蒸汽中的腐蚀研究
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  zr
Lead zirconium titanate (PZT) films (Zr/Ti=45:55) with a high dielectric constant are prepared successfully on the low-resistance Si substrate in sol-gel dip-coating process with PT film used as the buffer layer.
      
The solid acids were prepared by mounting H2SO4 on TiO2 · nH2O and Zr(OH)4, respectively, followed by calcining at 823K.
      
To deal with this contradictory situation, insolvable zirconium tricarboxybutylphosphonate (Zr(PBTC)) powder was employed to make a composite with SPEEK polymer in an attempt to improve temperature tolerance of the membranes.
      
SPEEK/Zr(PBTC) composite membranes were obtained by casting a homogeneous mixture of Zr(PBTC) and SPEEK in N,N-dimethylacetamide on a glass plate and then evaporating the solvent at 60°C.
      
Results showed significant improvement not only in temperature tolerance, but also in methanol resistance of the SPEEK/Zr(PBTC) composite membranes.
      
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The cumulative yields of 95Zr, "Mo, 103Ru, 106Ru, 144Ce and 147Nd in the fission of 238U induced by neutrons of 14.9 MeV were determined absolutely by radiochemical method. The 14.9±0.46 MeV neutrons were produced in the T (D,n)'He reaction using the 600kV Cockcroft-Walton type accelerator. The neutron flux varied between 2×109 and 1010 neutrons/sec. In this work the natural uranium was used as material of sample and standard targets. The standard targets were prepared by molecular plating and the sample...

The cumulative yields of 95Zr, "Mo, 103Ru, 106Ru, 144Ce and 147Nd in the fission of 238U induced by neutrons of 14.9 MeV were determined absolutely by radiochemical method. The 14.9±0.46 MeV neutrons were produced in the T (D,n)'He reaction using the 600kV Cockcroft-Walton type accelerator. The neutron flux varied between 2×109 and 1010 neutrons/sec. In this work the natural uranium was used as material of sample and standard targets. The standard targets were prepared by molecular plating and the sample targets were uranium metal disks with masses ranging from 1.5 to 3 gramms. The absolute fission rate of the sample target was measured by double fission ionization chamber.The irradiated targets were dissolved, and carriers of each element were added. By means of modified standard radiochemical procedures the above mentioned nuclides were separated, purified and mounted. The radioassay of radionuclides separated from the sample was carried out by using two types of detectors, namely, a low background counter for β-counting, and Nal(Tl) crystal detector coupled with a single channel analyzer for γ-counting. Both of the detectors were calibrated by 4π/β-γ coincidence counting.The cumulative yields determined by the above mentioned method are listed in following table. The errors given in the table are total errors including statistical and systematic errors. The yield values of this work are found to be in good agreement with most reported yields within error limits.

本文叙述了用放化方法测定14.9MeV中子诱发~(238)U裂变时的裂变产物~(95)Zr,~(99)Mo,~(103)Ru,~(106)Ru,~(144)Ce和~(147)Nd的绝对累计产额,其结果分别为(4.96±0.22)%,(5.44±0.20)%,(4.75±0.23)%,(2.51±0.13)%,(4.01±0.21)%和(2.13±0.11)%。裂变率是用双裂变室测量的,裂变产物核的衰变率用经4πβ-γ符合法刻度过的低本底2πβ卢和NaI(T1)测量仪测定。

The far infrared evaporation technology for treatment of lower-middle level radioactive waste liquid was investigated. The effects of the heater, distance, negative pressure and pH on cleaning factors of nuclides (137Cs, 90Sr, 147Pm, 95Zr-95Nb) and evaporaton rate were examined. About 0.7 tons of the medium liquid waste was treated; radioactive concentration of the condensate was 1×10-9Ci/l. The concentration factor was 35; resulted residue was in semi-solid state needing further solidification.

本文研究了用远红外蒸发技术处理中放废液的工艺条件及影响因素。探讨了远红外加热器的加热距离、系统负压、废液的pH值对各种核素(~(137)Cs、90Sr、~(147)Pm、~(95)Zr-~(95)Nb)和1AW废液的蒸发速率和去污因数影响。并对本所0.7吨中放废液进行了实际处理,二次蒸汽冷凝液的放射性浓度为1×10~(-9)Ci/l,浓缩倍数35,蒸残液已近半固体状态,需要进一步固化处理。

UO_2-Zr-2 is an ideal ceramet fuel. As an exemplification with this fuel, this paper emphatically elucidates the irradiation theory of ceramet fuel and its application in the design of ceramet fuel phase fraction and of fuel lparticle diameter. From the point of view of the irradiation theory and the consideration for sandwich rolling, the suitable volume fraction of UO_2 phaseof 25% and diameter of UO_2 particle of 100±15μm are selected.

UO_2-Zr-2是一种理想的金属陶瓷燃料。本文以该燃料为例,着重阐述金属陶瓷燃料辐照理论及其在燃料相含量和燃料颗粒尺寸设计中的应用,并由辐照理论观点和压力加工方面考虑,UO_2相体积含量宜取25%,UO_2颗粒直径宜取100±15微米。

 
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