助手标题  
全文文献 工具书 数字 学术定义 翻译助手 学术趋势 更多
查询帮助
意见反馈
   模拟堆芯 的翻译结果: 查询用时:0.013秒
图标索引 在分类学科中查询
所有学科
更多类别查询

图标索引 历史查询
 

模拟堆芯
相关语句
  simulation core
     Zero Power Experimental Assembly of Nuclear Power Plant Simulation Core
     核电站模拟堆芯零功率实验装置
短句来源
  “模拟堆芯”译为未确定词的双语例句
     As the widely used severe accident analysis computer codes, SCDAP/RELAP5 and MELCOR codes have adopted the models based on different theories to simulate the core degradation and reactor vessel lower head failure.
     SCDAP/RELAP5与MELCOR程序是目前得到广泛使用的两个严重事故分析程序,它们在模拟堆芯溶化及压力容器下封头失效过程中采用了基于不同理论的计算模型。
短句来源
     Khan's open lattice core modeling is used in the country. A 2×2rod bundle is developed to simulate the 17×17 rod bundle of prototype. For the purposeof 600MWe reactor hydraulic simulation test and core modeling, a turbine especially madeand an electrode that are located inside the model assemble are used to measure flow ratedistribution and flow mixing factors in the lower plenum respectively.
     在国内首次应用E.U.Khan压水堆开式栅格堆芯模拟理论,用2x2棒束模拟原型17x17棒束,用特殊研制的内磁式涡轮流量计测量堆芯入口流量分配,微型电导电极测量下空腔流动交混,完成了600MWe反应堆水力模拟堆芯的设计、实验等工作。
短句来源
     A tank to simulate a fuel assembly's environment and mechanical boundary condition is designed. In aseismatic reactor core test,the nonlinear vibrational behavior of the fuel assembly is studied.
     设计1个能模拟堆芯燃料组件工作环境和力学边界条件的台架,研究板状燃料组件的非线性振动行为。
短句来源
  相似匹配句对
     Simulated annealing algorithm for reactor incore design optimizations
     模拟退火算法优化堆芯设计
短句来源
     Zero Power Experimental Assembly of Nuclear Power Plant Simulation Core
     核电站模拟堆芯零功率实验装置
短句来源
     Simulation of distillation process
     精馏过程的模拟
短句来源
     Statistical Simulation
     统计模拟
短句来源
查询“模拟堆芯”译词为用户自定义的双语例句

    我想查看译文中含有:的双语例句
例句
为了更好的帮助您理解掌握查询词或其译词在地道英语中的实际用法,我们为您准备了出自英文原文的大量英语例句,供您参考。
  simulation core
Hypothesis 2 The master design and simulation core system choosen should be well suited for concept embodiment as well as detail design.
      
In a second step, the requirements of the simulation core on the generated scene have to be formulated.
      
Name of the net class extension used by cinsim-gui to define simulation sets for the simulation core of the CINSim project.
      
Physiologically-based crop models form the agronomic simulation core of GT-AgroPlan.
      
The simulation is performed by the simulation core, to be controlled at the command-line.
      


This paper mainly describes a part of structure size and related matter com-positions of core,fuel elements,and eontrolrods etc.in zero power experimen-tal assembly of nuclear power plant simulation core.

本文主要介绍核电站模拟堆芯零功率实验装置中的堆芯、燃料元件和控制棒等部分的结构尺寸和有关的材料成分。

In service fuelling and refuelling of PHWR is done continuously and the discharge direction of two adjacent channels is opposite. The neutron flux distribution, power distribution, burnup distribution of fuel bundles, effective multiplication factor, the effect of absorber, booster and water level, channel temperature rising, channel flow and other interest physical parameters can be given by solving three dimension two group neutron diffusion in core fuel management computer code through finite element numerical...

In service fuelling and refuelling of PHWR is done continuously and the discharge direction of two adjacent channels is opposite. The neutron flux distribution, power distribution, burnup distribution of fuel bundles, effective multiplication factor, the effect of absorber, booster and water level, channel temperature rising, channel flow and other interest physical parameters can be given by solving three dimension two group neutron diffusion in core fuel management computer code through finite element numerical method. Choosing arbitary triangular prizm elements and quatraanqular prizm elements to simulate reactor core. Automatical mesh formation and manual mesh formation are jointly adopted. This code has both automatic refuelling capability and manual refuelling capability. In order to extend its application, the conversion of irradiated core into another specific core and recalculation functions are provided to simulate reactor core operation and in core fuel management. The adopted Techebyshev acceleration convergency method make the calculation precise and rapid.

重水动力堆的装换料是在带功率下进行的、相邻管道换料方向相反的双向连续换料。用有限元法编制了三维二群中子扩散堆芯燃料管理程序,给出中子通量分布、功率分布、燃料束的比燃耗分布,有效增殖系数,吸收棒、点火棒和水位的效应,管道温升和管道流量以及其它关心的物理量。使用任意三棱柱元素和四棱柱元素,较真实地模拟反应堆边界。网格的剖分采用自动和人工相结合。程序既有自动装换料的功能,又有人工装换料的功能;为了使它有广泛的适应性,还特别设置了从辐照过的堆芯转变为另一种特定堆芯,并重新开始计算的功能。它可综合模拟堆芯运行和燃料管理。采用源迭代和切比雪夫加速收敛技巧使程序精度高,运算速度快。用3D-IAEA和3DPHWR对程序进行了考核,达到了预期的效果。

In service fuelling and refuelling of PHWR is done continuously and the discharge direction of two adjacent channels is opposite. The neutron flux distribution, power distribution, burnup distribution of fuel bundles, effective multiplication factor, the effect of absorber, booster and water level, channel temperature rising, channel flow and other interest physical parameters can be given by solving three dimension two group neutron diffusion in core fuel management computer code through finite element numerical...

In service fuelling and refuelling of PHWR is done continuously and the discharge direction of two adjacent channels is opposite. The neutron flux distribution, power distribution, burnup distribution of fuel bundles, effective multiplication factor, the effect of absorber, booster and water level, channel temperature rising, channel flow and other interest physical parameters can be given by solving three dimension two group neutron diffusion in core fuel management computer code through finite element numerical method. Choosing arbitary triangular prizm elements and quatraanqular prizm elements to simulate reactor core. Automatical mesh formation and manual mesh formation are jointly adopted. This code has both automatic refuelling capability and manual refuelling capability. In order to extend its application, the conversion of irradiated core into another specific core and recalculation functions are provided to simulate reactor core operation and in core fuel management. The adopted Techebyshev acceleration convergency method make the calculation precise and rapid.

重水动力堆的装换料是在带功率下进行的、相邻管道换料方向相反的双向连续换料。用有限元法编制了三维二群中子扩散堆芯燃料管理程序,给出中子通量分布、功率分布、燃料束的比燃耗分布,有效增殖系数,吸收棒、点火棒和水位的效应,管道温升和管道流量以及其它关心的物理量。使用任意三棱柱元素和四棱柱元素,较真实地模拟反应堆边界。网格的剖分采用自动和人工相结合。程序既有自动装换料的功能,又有人工装换料的功能;为了使它有广泛的适应性,还特别设置了从辐照过的堆芯转变为另一种特定堆芯,并重新开始计算的功能。它可综合模拟堆芯运行和燃料管理。采用源迭代和切比雪夫加速收敛技巧使程序精度高,运算速度快。用3D-IAEA和3DPHWR对程序进行了考核,达到了预期的效果。

 
<< 更多相关文摘    
图标索引 相关查询

 


 
CNKI小工具
在英文学术搜索中查有关模拟堆芯的内容
在知识搜索中查有关模拟堆芯的内容
在数字搜索中查有关模拟堆芯的内容
在概念知识元中查有关模拟堆芯的内容
在学术趋势中查有关模拟堆芯的内容
 
 

CNKI主页设CNKI翻译助手为主页 | 收藏CNKI翻译助手 | 广告服务 | 英文学术搜索
版权图标  2008 CNKI-中国知网
京ICP证040431号 互联网出版许可证 新出网证(京)字008号
北京市公安局海淀分局 备案号:110 1081725
版权图标 2008中国知网(cnki) 中国学术期刊(光盘版)电子杂志社