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裂变物质
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  fission material
     The detector can been used to determine the burnup, cooling time and the contents of whole plutonium and whole fission material in spent fuel assemblies of the PWR and BWR types at a reprocessing and storage facility.
     叉形探测器可用于后处理和贮存工厂中PWR和BWR型的乏燃料组件的燃耗、冷却时间、总钚和总裂变物质含量的测定。
短句来源
  “裂变物质”译为未确定词的双语例句
     The liquid solution is used for nuclear fuel in the solution reactor.
     溶液堆使用裂变物质的水溶液为核燃料。
短句来源
  相似匹配句对
     The liquid solution is used for nuclear fuel in the solution reactor.
     溶液堆使用裂变物质的水溶液为核燃料。
短句来源
     Fission of Narration
     叙事的裂变
短句来源
     On Substance
     论物质
短句来源
     Basic knowledge of analytical reagents-biological material of high molecular weight
     生物高分子物质
短句来源
     A principle of fission and conformity
     主体的裂变及整合
短句来源
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  fission material
Thus 245 Cm was selected as the baseline fission material.
      
  fissile material
This fuel type differs significantly from other fuel elements with respect to shape, composition and fissile material content.
      
Fissile Material Cut-off Treaty), the discussion focuses on highly enriched uranium, because this seems to be of highest strategic relevance.
      
Fuels for FBRs have significantly higher concentration of fissile material than in thermal reactors, with a matching increase in burn-up.
      
For the mode of accumulation of 233U it was assumed for calculations that plutonium can be used as additional fissile material to provide neutrons for 233U production.
      
A Pragmatic Approach for Negotiating a Fissile Material Cut-Off Treaty
      
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  fissioner
The amount of the edge effect for a finite-size fissioner slab is demonstrated with calculations for vacuum conditions and for argon under a pressure of 0.25 atm.
      


Under a prolong time neutron irradiation of 232Th by a strong constant neutron flux, a part of 232Th atoms will be converted into a series other nuclides as a result of successive neutron interaction. These neutron born daughter nuclides of 232Th consist of fissile nuclides such as 233U,235U,239Pu,241Pu, … and fertile nuclides, such as 233Pa,234U,236U,237Np,238Pu etc. As a rule the concentration of each daughter nuclide starts from zero and then increases gradually as the irradiation proceeds until reaching...

Under a prolong time neutron irradiation of 232Th by a strong constant neutron flux, a part of 232Th atoms will be converted into a series other nuclides as a result of successive neutron interaction. These neutron born daughter nuclides of 232Th consist of fissile nuclides such as 233U,235U,239Pu,241Pu, … and fertile nuclides, such as 233Pa,234U,236U,237Np,238Pu etc. As a rule the concentration of each daughter nuclide starts from zero and then increases gradually as the irradiation proceeds until reaching a saturated value and then decreases at a similar rate as the decreasing rate of 232Th. A reactor fueled with thorium and its whole family of neutron born daughter nuclides, with each daughter nuclide at its own saturated concentration, may possess some interesting properties. A preliminary study of the feasibility of such constellation type fissile fuels reactor is presented.

从分析钍在持续中子辐照过程中各代子体含量的演变出发,着重研究有多代子体均达到各自的饱和值时的情况和所具有的特性,提出星座型裂变物质核反应堆的物理构想,并就此堆的特性和应用前景作了简单阐述和讨论。

The principles, methods and equipments of burn-up measurement for power reactor spent fuel assembly using passive and active techniques are described. The fork detector, a simple, rapid and reliable measurement system, which is composed of an ion chamber and a fission chamber, has been used to measure the burn-up of LWR assemblies. The deviation between measured results and declared values can be made within 1 %. A deviation of 1 % can also be reached by using high-resolution gamma-ray spectrometry(HRGS) technique....

The principles, methods and equipments of burn-up measurement for power reactor spent fuel assembly using passive and active techniques are described. The fork detector, a simple, rapid and reliable measurement system, which is composed of an ion chamber and a fission chamber, has been used to measure the burn-up of LWR assemblies. The deviation between measured results and declared values can be made within 1 %. A deviation of 1 % can also be reached by using high-resolution gamma-ray spectrometry(HRGS) technique. The content of fissile materials in spent fuel assemblies can be determined from measured gamma-ray or neutron information.

概要综述了用无源和有源非破坏性分析技术测量动力堆乏燃料组件燃耗的基本原理、方法和实验装置。由电离室和裂变室组成的标准叉型探测器具有性能稳定可靠、分析速度快、操作简单、携带方便等优点。当前,它对LWR组件的燃耗测量值和申报值的偏差在±1%以内。用高分辨γ谱方法(HRGS)测量组件的燃耗,也能达到同样的精度。根据测量得到的中子计数或γ放射性,可以确定组件中可裂变物质的含量。

A fork detector has been constructed by making use of gross gamma and passive neutron methods. The detector can been used to determine the burnup, cooling time and the contents of whole plutonium and whole fission material in spent fuel assemblies of the PWR and BWR types at a reprocessing and storage facility.

采用总γ和无源中子测量方法建立了叉形探测器。叉形探测器可用于后处理和贮存工厂中PWR和BWR型的乏燃料组件的燃耗、冷却时间、总钚和总裂变物质含量的测定。

 
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