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全堆芯
相关语句
  core-wide
     CASTA-1: Core-wide and Subchannel Three-dimensional Two-fluid Transient Analysis Code for Water Reactors
     CASTA-1:水堆全堆芯和子通道三维两流体瞬态分析程序
短句来源
     Since the CASTA-1 code also includes the treatment of transverse boundary conditions, it not only can be applied in core-wide analysis, but also in subchannel analysis.
     由于该程序还考虑了测边界条件的处理,因此它不仅能用于全堆芯分析,还能用于子通道分析。
短句来源
  core-wise
     FAST NODAL CORE-WISE GREEN′S FUNCTION METHOD FOR NEUTRON DIFFUSION CALCULATIONS
     计算中子扩散方程的全堆芯格林函数快速节块方法
短句来源
     APPLICATION OF THE CORE-WISE GREEN'S FUNCTION METHOD TO IN-CORE FUEL MANAGEMENT AND OPTIMIZATION FOR PWR
     全堆芯格林函数方法在核电厂堆芯燃料管理及优化中的应用
短句来源
     THE CORE-WISE GREEN'S FUNCTION METHOD FOR PWR DIFFUSION CALCULATION
     用于压水堆扩散计算的全堆芯格林函数方法
短句来源
     Green’s Function Library for Core-Wise Green’s Function Method
     全堆芯格林函数方法的格林函数库的建立
短句来源
  whole-core
     The irradiation and whole-core demonstration indicate that the fuel elements were dimensionally sta-ble.
     辐照和全堆芯试用表明:元件外形尺寸稳定;
短句来源
  “全堆芯”译为未确定词的双语例句
     Whole Core Diffusion Calculation for China Advanced Research Reactor
     中国先进研究堆全堆芯扩散计算
短句来源
     1. Flow distribution calculation of whole core.
     1.全堆芯流量分配计算。
短句来源
     The perturbation diffusion calculation method is used to establish the Green’s function library for Core wise Green’s function method (CGFM).
     提出了利用微扰正向扩散计算方法的思想 ,建立了全堆芯格林函数方法 (CGFM )中的格林函数库 .
短句来源
     Using the product of reconstructed power times flux form factor, the real power distribution of test loop assemblies and core fuel assemblies for high flux engineering test reactor is calculated. The time (or burn up step), assembly position, fuel circle number, and angle direction at which the core hot spot factor appeared are also given.
     利用精细注量率重组和注量率形状因子的乘积方法对高通量工程试验堆的考验回路和堆芯燃料组件内的功率分布进行重组 ,并给出全堆芯的热点因子及其出现的时间 (燃耗步 )、组件位置、轴向位置、径向环位置和环向角度
短句来源
     The neutronics analysis of China Advanced Research Reactor is carried out with the diffusion method by using the whole core module in this paper.
     基于物理启动、同位素生产以及空间燃耗不同考虑的全堆芯模型,采用少群扩散方法对中国先进研究堆(CARR)堆芯进行计算。
短句来源
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  core-wide
Comparison of core-wide mean pigment concentrations suggested that cores recovered from within the photic zone are influenced by benthic algal production and will not represent either historical or current ecological dynamics in the water column.
      
Core-wide, as well as hot channel loadings on the fuel clad will need to be addressed.
      
From these comparisons it can be concluded that, on a core-wide basis, THERMIT can accurately predict the core exit temperature distribution.
      
In addition to the above mentioned validation efforts, the core-wide and transient capabilities have also been assessed.
      
This effort has been aimed at validating THERMIT for both subchannel and core-wide applications.
      
  whole-core
1 m sediment cores were collected from Lake Baikal during a summer cruise in 1996 and analysed for whole-core susceptibility.
      
The whole-core sensor gives a smoothed equivalent to a 'moving average' curve of magnetic susceptibility while the surface scanner can give fine resolution (ca.
      
Additional comparisons are still required in this area, particularly for the whole-core depletion calculations.
      
A number of the inferred polarity reversal boundaries deduced from the whole-core spinning are confirmed by the results of the discrete sample study.
      
Generally, excellent agreement is seen between the subsample data and shipboard whole-core measurements of both NRM and susceptibility.
      
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This paper presents a two-fluid model applied in thermal hydraulic transient analysis of nuclear reactor cores. This model involves separate partial differential equations expressing conservations of mass, momentum, and energy for each individuel fluid phase, it does not require the phases to move with the same velocity or to have equal temperatures. CASTA-1 code using this model solves the three-dimensional equations in rectangular coordinates. This code offers the choice of either pressure or velocity boundary...

This paper presents a two-fluid model applied in thermal hydraulic transient analysis of nuclear reactor cores. This model involves separate partial differential equations expressing conservations of mass, momentum, and energy for each individuel fluid phase, it does not require the phases to move with the same velocity or to have equal temperatures. CASTA-1 code using this model solves the three-dimensional equations in rectangular coordinates. This code offers the choice of either pressure or velocity boundary conditions at the top and bottom of the core. Since the CASTA-1 code also includes the treatment of transverse boundary conditions, it not only can be applied in core-wide analysis, but also in subchannel analysis. The comparison of the computational results for reactor core of PWR and BWR are also presented.

本文给出了用于核反应堆堆芯热工水力瞬态分析的两流体模型。该模型分别列出每一相的质量、动量和能量差分守恒方程,不需要两相有相同的速度和温度。按该模型编制的CASTA-1程序能求解直角座标系的三维方程组。该程序允许选择堆芯顶部和底部的压力或速度边界条件的任意组合。由于该程序还考虑了测边界条件的处理,因此它不仅能用于全堆芯分析,还能用于子通道分析。文中还给出了压水堆和沸水堆堆芯计算实例的比较。

U_3Si_2-Al dispersion plate-type fuel element is a high Uranium-densityfuel recently developed for research reactors.The irradiation and whole-core demonstration indicate that the fuel elements were dimensionally sta-ble.No indication of fission product leaked from the plates was detected.The swelling of U_3Si_2 particles is a linear function of the fission densityup to 98% burnup.U_3Si_2 is compatible with the aluminum matrix andcladding in conditions of both fabrication and irradiation.U_3Si_2-Al disper-sion...

U_3Si_2-Al dispersion plate-type fuel element is a high Uranium-densityfuel recently developed for research reactors.The irradiation and whole-core demonstration indicate that the fuel elements were dimensionally sta-ble.No indication of fission product leaked from the plates was detected.The swelling of U_3Si_2 particles is a linear function of the fission densityup to 98% burnup.U_3Si_2 is compatible with the aluminum matrix andcladding in conditions of both fabrication and irradiation.U_3Si_2-Al disper-sion fuel with 4.8g/cm~3 uranium density is a suitable LEU fuel for re-search reactor.

U_3Si_2-Al 弥散型板状燃料元件是新发展的高铀密度的研究堆燃料.辐照和全堆芯试用表明:元件外形尺寸稳定;无裂变产物泄漏;直到燃耗达98%时,U_3Si_2颗粒肿胀都是裂变密度的线性函数;U_3Si_2与铝基体和铝包壳在制造和辐照中都是相容的。芯体铀密度最高达4.8g(U)/cm~3的 U_3Si_2-Al 燃料都是适合研究堆使用的低浓铀燃料.

A fast nod3l core-wise Green′s function method for neutrond diffusion calculations wasdeveloped.A new idea of building core-wise Green′s function library was proposed,and thecomputer code CGFM was encoded.It was qualified by some benchmark problems and theQinshan Nuclear Power Plant problem,The numerical results demonstrated that this methodis 10 time faster than nodal Green′s function method(NGFM)while keeping given preci-sion.

导出了全堆芯格林函数快速节块方法理论模型,提出了对各个节块逐次扰动进行正向扩散计算建立格林函数库的思想,研制了相应软件CGFM,对一系列基准问题和我国秦山核电厂的问题进行了校核,计算结果表明,本文方法在保证一定的计算精度下,计算速度比先进节块方法NGFM快10倍左右。

 
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