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   堆芯 在 核科学技术 分类中 的翻译结果: 查询用时:0.084秒
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堆芯     
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  core
On the non-compactness of the core of nonatomic convexσ-continuous measure games
      
This paper concerns with the core of nonatomic games of form f(μ), whereμ is a nonatomic nonnegative measure and f is a continuous convex function on the domain ofμ.
      
The main result of this paper is that the core of the game is not compact under the norm topology unless the game itself is a measure.
      
This shows the largeness of the core in a sense other than that defined by Sharky for finite cases.
      
For example, in water, PCL and PAA formed core-shell nanospheres due to interpolymer hydrogen bonding.
      
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  reactor core
A new supercritical water-cooled reactor (SCWR) core structure (the mixed reactor core) and a new fuel assembly design (two-rows FA) are proposed.
      
By simulating the whole reactor core, the detailed mass flow distribution in the core was obtained.
      
The possibility is discussed of using the obtained data in simulating emergency conditions in the reactor core.
      
The interaction of nuclear reactor core melt with oxide sacrificial material of localization device for a nuclear power plant wi
      
The neutron spectrum at the center of the reactor core was measured by the neutron activation method using the a priori spectrum as a superposition of partial fission and evaporation spectra.
      
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  in-core
A hybrid OCBT structure is also proposed where an in-core cluster binary tree is combined with a large out-of-core file.
      
An in-core/out-of-core method for solving large scale assignment problems
      
We describe how the shortest augmenting path method can be used as basis for a so called "in-core/out-of-core" approach for solving large assignment problems in which the data cannot be kept in central memory of a computer.
      
We introduce several strategies which enable to keep the working subgraph sparse throughout the procedure and even lead to an all in-core code which is faster than the basic shortest augmenting path code.
      
Using matrices from different areas (Interior Point Methods of linear programming and Finite Element Methods), we evaluate our sequential in-core hypermatrix sparse Cholesky implementation.
      
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  active core
From that point of view, the secondary and quaternary structure analysis of ADNF9, an active core fragment peptide of ADNF, was performed by circular dichroism (CD) and sedimentation equilibrium.
      
coli merodiploids carrying F-factor with ilv-thi chromosome fragment the activity of RNA polymerase is not increased, and there is no excess of free active core-enzyme or sigma-factor.
      
Parameters of active core and scheme of fuel reloading were considered to be the same as for standard operation in uranium cycle.
      
Mathematical models of gonorrhoea transmission can predict increasing incidence with decreasing sexual activity in the population, due to a resultant concentration of sexual activity in an active 'core' group.
      
The proteolytically active core is formed by the 20S proteasome.
      
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In-core fuel management plays an important role for better utilization of fuel, improving core characteristics and consequently decreasing the cost of electricity generated by nuclear power stations. With partial refuelling scheme, one may have a higher discharge burnup for the same enrichment of fuel loaded in core. A multi-batch core with different enrichment fuels enables to flatten the radial power distribution and therefore to raise the average power density. Quite uniform discharge burnup can be achieved...

In-core fuel management plays an important role for better utilization of fuel, improving core characteristics and consequently decreasing the cost of electricity generated by nuclear power stations. With partial refuelling scheme, one may have a higher discharge burnup for the same enrichment of fuel loaded in core. A multi-batch core with different enrichment fuels enables to flatten the radial power distribution and therefore to raise the average power density. Quite uniform discharge burnup can be achieved by the multi-batch, OUT-IN fuel shuffling scheme. The discharge burnup and K∞ are directly influenced by the amount of fresh assemblies loaded in each refuelling.The cycle length, the type of standby fuel and the enrichment of fresh fuel etc., that influence the fuel utilization, load factor and the fuel cycle cost of the station, should be correctly selected.This paper presents a survey of the calculation programs for in-core fuel management and discusses core fuel loading patterns and shuffling schemes, fuel enrichment, number of fresh assemblies loaded at each refuelling, various standby fuel assemblies, burnup cycle length and stretch-out operation. For comparison, some of the above-mentioned subjects have been calculated.Various factors that have effect on uranium utilization can be seen from the calculated results. A comprehensive review and selection of proper parameters for fuel management are important for the design of a nuclear power station.

本文簡要介紹了堆芯燃料管理所使用的計算程序,討論了堆芯燃料的装載及更換方式、燃料加浓度的选择、每次換料时更換燃料組件的数量、备用燃料的选择、循环寿期的选定以及堆芯延迟換料的运行等。对其中一些內容計算了几种方案以进行比较。由計算结果可以看到影响經济利用核燃料的各种因素,在設計电站压水堆时需要綜合考虑,恰当选择。

This paper describes a method for embedding the sheathed thermocouples inthe aluminum claddings of some fuel elements of experimental reactors byultrasonic welding technique,and the measurement results of the claddingtemperature of fuel elements in reactors.By means of this method,the jointbetween the sheathed thermocouple and the cladding of fuel element can bemade to very tight,and there isn't bulge on the cladding surface,and the shea-thed thermocouples are embedded strongly and reliably,therefore essentialmeans...

This paper describes a method for embedding the sheathed thermocouples inthe aluminum claddings of some fuel elements of experimental reactors byultrasonic welding technique,and the measurement results of the claddingtemperature of fuel elements in reactors.By means of this method,the jointbetween the sheathed thermocouple and the cladding of fuel element can bemade to very tight,and there isn't bulge on the cladding surface,and the shea-thed thermocouples are embedded strongly and reliably,therefore essentialmeans is provided for acquirement of stable and dynamic state date of the cla-dding temperature of in-core fuel elements.

本文介绍一种应用超声焊接技术在几种实验堆燃料元件铝包壳上埋设铠装热电偶的方法及元件包壳温度随堆测量结果。应用这种方法可以使得铠装热电偶与元件包壳贴合十分紧密,包壳表面没有突起部分,而且铠装热电偶埋设牢固、可靠,为取得堆芯燃料元件包壳温度的稳态与动态测量数据提供了重要的手段。

The safety experiments carried out in Research Center of Nuclear Energy atMol are presented.The experiments were made in an in-pile sodium loop.Thetested LMBFR fuel assemblies were irradiated in a reactor.There was a bloc-kage cage in the assemblies.The cooling flow within the cage has been artifici-ally interrupted in order to cause sodium boiling and fuel melting.The experim-ents demonstrated that the possibility of pin failure propagation due to a block-age in the channel could be excluded.

本文介绍了在莫尔核能研究中心进行的快堆安全实验。实验工作在堆内钠回路中进行。被试验的快堆元件棒束在堆内辐照。在组件中有一个堵塞装置。人为地切断堵塞装置中的冷却流量而引起钠沸腾和元件熔化事故。试验表明,由于堆芯流道堵塞而引起元件损坏事故蔓延的可能性可以排除。

 
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