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群截面
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  group cross section
     Generation of minor group cross section library for micro beryllium-reflex layer fast reactor
     微小型铍反射层快中子堆专用群截面数据库的制作
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  “群截面”译为未确定词的双语例句
     Study of NJOY Input Parameters for Update of WIMS Library
     WIMS多群截面库更新时NJOY输入参数研究
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     For assemblies of different sizes and different concentration of ~6Li,numerical calculations are using the 30 group library derived from ENDF/B-Ⅵ and JEF-2.2.
     计算中使用了30群截面数据,微观数据来自ENDF/B-VI及JEF-2.2。
短句来源
     GENERATION OF THE 69-GROUP CROSS SECTION LIBRARY TPLIB-94
     TPLIB-94 69群截面库的研制
短句来源
     THE THEORY OF LOOSE NETWORK SND GROUP-CUT IN THE OPTIMIZATION OF TIME-COST
     时间费用优化中松驰网络与群截面理论
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     Man-Machine Interaction Model and Its Algorithm for the Method of Cut Sets in Optimal Technology of Network Plan
     网络计划优化中群截面方法的人机对话模型及算法设计
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  相似匹配句对
     GENERATION OF THE 69-GROUP CROSS SECTION LIBRARY TPLIB-94
     TPLIB-94 69截面库的研制
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     ON LAGRANGE BISECTIONS OF SYMPLECTIC GROUPOIDS
     关于辛胚的拉格朗日双截面
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     Group B contains T.
     B由T .
短句来源
     HOMOMORPH-GROUP
     态
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     The Drawing of Elliptic Cross Sections
     椭球体的截面画法
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  group cross section
For each burnup step, the neutron spectrum and effective multi group cross section are evaluated by either MVP or SRAC95.
      
ORIGEN2.1 performs the burnup calculation using these one group cross section.
      
The Advisory Group recommends that for the reactions in the two tables, a fine group cross section library would be very valuable.
      
The production of a comparison of one-group cross section sets for all of the relevant nuclides should result from this work.
      
  group cross-section
In addition a link to a multi-group cross-section generation code, for example ECCO, be considered.
      
Temperature dependent, 53-group cross-section data used in the 3DB calculations were generated in lDX, as described in Section HI.
      


In the in-core fuel management model that has been developed in this paper, the fast group parameter is calculated using B_1 approximation and the thermal group parameter using the first flight collision probability method, but the critical and depletion calculations are based on the coarsemesh method.The nodal imbedded calculation, combined with the coarsemesh calculation, can give ths detailed flux and power distribution in assemblies.

在本文提出的堆芯燃料管理计算模型中,快群参数用B_1近似计算;热群截面的计算采用首次飞行碰撞几率法;而堆芯临界、燃耗计算是建立在粗网展开法的基础上。与粗网计算相配合的节块嵌入计算,能给出燃料组件内的精细通量、功率分布。

The paper analyzes the variaton in neutron diffusion few-group cross section behavior subjected to fuel burnup and critical boron concentration in a core. The influences of the behavior on the core excess reactivity, crirical boron concentration, power distribution and the yield of isotopes are also analyzed. A reactor core of small-medium sized nuclear power plant is analyzed as an example.

本文以一个中小型核电站堆芯为例,分析计算了中子扩散少群截面参数随燃料的燃耗、堆芯的临界硼浓度的变化特性,以及这种特性对堆芯剩余反应性、临界硼浓度、功率分布和同位素产量计算的影响。

Monte Carlo method was successfully used to simulate the physical process of neutron-gamma well logging including the emission and transport of neutrons, the capture of thermal neutrons, and the generation and transport of photons. The Neutron-gamma flux to the detector was calculated with a direction probability method. The multiple group neutron cross-section data were used in the transport of neutrons, and the point cross section data were used in the transport of photons. The calculated values of the photon...

Monte Carlo method was successfully used to simulate the physical process of neutron-gamma well logging including the emission and transport of neutrons, the capture of thermal neutrons, and the generation and transport of photons. The Neutron-gamma flux to the detector was calculated with a direction probability method. The multiple group neutron cross-section data were used in the transport of neutrons, and the point cross section data were used in the transport of photons. The calculated values of the photon energy peak were in good agreement with the selected value.

应用蒙特卡罗方法,成功地模拟了中子伽马测井的物理过程和中子的输运过程、热中子的俘获以及中子伽马射线的产生和输运过程.用指向概率方法计算了中子伽马射线对探洲器的通量贡献,用群截面数据库模拟中子,用点截面数据模拟伽马光子,计算绘出的中子伽马能谱峰值与所选择的特征能量非常吻合,从而证明了蒙特卡罗方法在核测井领域应用的可行性.

 
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