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
   critical assembly 的翻译结果: 查询用时:0.008秒
图标索引 在分类学科中查询
所有学科
核科学技术
更多类别查询

图标索引 历史查询
 

critical assembly
相关语句
  临界装置
     NEUTRON SPECTRA MEASUREMENT IN A FAST CRITICAL ASSEMBLY WITH ~6Li-SEMICONDUCTOR SANDWICH SPECTROMETER
     用~6Li半导体谱仪测量临界装置中子能谱
短句来源
     A Modification Design and Adjusting Test for Instruments and Control System of Critical Assembly
     临界装置仪控系统的更新设计与调试
短句来源
     A fission chamber is designed to monitor the power of critical assembly which operated from 0.01W to 1000W. The fission chamber has three different sensitivity region.
     为了监测临界装置宽范围的运行功率,设计了一个有三个灵敏区的裂变电离室,三个灵敏区放置在活性区不同位置,可以实现从0.01-1000W的功率监测。
     A MODIFICATION DESIGN AND ADJUSTING TEST FOR INSTRUMENTS AND CONTROL SYSTEM OF CRITICAL ASSEMBLY
     临界装置仪控系统的更新设计与调试
短句来源
     The tritium production rate and its distribution, in a 6LiD semisphere on a critical assembly neutron source are measured with a 6Li sandwich gold-silicon surface barrier detector. Then tritium production rate and the average tritium production length of the neutrons in the whole 6LiD sphere are derived from approximate sphere symmetry.
     用临界装置中子源,夹心~6Li金硅面垒探测器,进行了~6LiD半球的中子造氚测量,得到了中子造氚分布,并用近似的球对称得到了全球的造氚率及平均造氚长度。
短句来源
更多       
  “critical assembly”译为未确定词的双语例句
     THE CRITICAL ASSEMBLY OF SHANGHAI INSTITUTE OF NUCLEAR RESEARCH DIVISION OF REACTOR TECHNOLOGY
     上海原子核研究所零功率实验装置
短句来源
     In this design, a critical assembly was the valve-cell which was a united body of an electrochemical cell and a sampling valve.
     在这个接口中,进样阀电化学池既具有薄层电化学池的功能,又作为微量液体进样阀,电化学薄层腔作为进样阀的定量管。
短句来源
  相似匹配句对
     SOME CRITICAL TECHNIQUES IN BOLT ASSEMBLY AUTOMATION
     螺栓装配自动化的关键技术研究
短句来源
     Fission chamber for critical assembly power momtor
     临界装置功率监测裂变室设计
     Critical Theory
     批判理论
短句来源
     On the Rights of Assembly
     论集会权
短句来源
     On X'-critical Graph
     边色数临界图
短句来源
查询“critical assembly”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。
  critical assembly
The neutron spectra at the center of the critical assembly core and in the analog BR-1 reactor are compared.
      
The results of reactivity-measurement experiments which were performed during the same period of time on a critical assembly simulating on the Nartsiss stand the neutron-physical characteristics of the Topaz-2 reactor to be used in space are given.
      
The measurements are performed in the thermal column of a BFS-2 critical assembly and in a thermal-neutron beam extracted from a BR-10 reactor.
      
Radiation dose received by a researcher in a critical assembly accident at Russian Federation Nuclear Center/All-Russian Scienti
      
A study of transient processes in hypothetical accidents in a fast critical assembly with a moderating reflector
      
更多          


This paper summarizes present research situation of central reactivity coef-ficients for fast reactors.They are considered to be great of significance:deve-loping the calculating methods of reactivity coefficients for various meterial sam-ples under different conditions,perfecting the experimental measuring techniqueson benchmark critical assemblies,and analysing the discrepancy between calcula-ting values and measuring values.

本文综述了快堆中心反应性系数的研究现状,认为发展不同条件下各种样品的反应性系数的计算方法,进一步完善基准装置上的实验测量技术,分析其计算值与测量值之间不一致的原因所在,是一件很有意义的工作。

In this parper, we briefly describe S_N method of solving the unsteady neutron transport equation in two-dimensional cylindrical geometry and give some calculation results. In order to test the reliability of the method, we have calculated 7 critical assemblies. When the number of the angular mesh joints is 4×7 and the number of the space mesh joints is over 7×7 in the uniform medium the calculation results agree with experiments and no negative flux appears. But in the ununiform medium, the number of...

In this parper, we briefly describe S_N method of solving the unsteady neutron transport equation in two-dimensional cylindrical geometry and give some calculation results. In order to test the reliability of the method, we have calculated 7 critical assemblies. When the number of the angular mesh joints is 4×7 and the number of the space mesh joints is over 7×7 in the uniform medium the calculation results agree with experiments and no negative flux appears. But in the ununiform medium, the number of the space mesh joints needs to be increased to 12×8. On YH1 the calculations with corrections of the negative flux for each time step in uniform medium need 2.7 Sec.—3.6Sec., the calculations without the corrections of the negative. flux need 1.5 Sec.—2.1 Sec. The calculations by vectoriged program need less than, 0.48 Sec., the speed of the calculation is about six times as much as before. This program can provide prompt space, spectrum and angular distribution of the neutron flux and some assembly parameters, such as time constant λ, effective multiplication-factor Ke, and so on.

本文简要地介绍了二维动态多速中子迁移方程的S_N解法,并给出一些计算结果。为了验证方法的可靠性,我们计算了七个临界装置。计算结果表明:在无反射层的均匀介质中,对角度的网点采取4×7,空间网点采取7×7以上,就可以得到满意的结果,不必作通量校正。但在加上反射层时,空间网点需增加到12×8。在YH1机上计算,对无反射层均匀介质,计算每个时间分点,作通量校正时需2.7-3.6秒,不作通量校正需1.5-2.1秒。程序向量化后计算每个时间分点需0.48秒以下,提高速度5倍左右。本计算程序可以给出瞬时中子通量的空间分布、能谱分布及角分布,同时给出装笠参数,时间常数λ,有效倍增因子K_6等。

A general description of the slightly enriched uranium fueled and light water moderated critical assembly of Shanghai Institute of Nuclear Research, Academia Sinica is given. Some experimental works carried out with it are also briefly presented.The main task of this facility is the research for PWR power plants. The core design is to simulate the clustered fuel assembly structure without box and the whole lattice arrangement of PWRs. It is also possible to simulate the chemical control of the reactivity...

A general description of the slightly enriched uranium fueled and light water moderated critical assembly of Shanghai Institute of Nuclear Research, Academia Sinica is given. Some experimental works carried out with it are also briefly presented.The main task of this facility is the research for PWR power plants. The core design is to simulate the clustered fuel assembly structure without box and the whole lattice arrangement of PWRs. It is also possible to simulate the chemical control of the reactivity by putting soluble boron poison into the light water moderator and reflecter. In addition, the following advantages are available: the pretty good flexibility of the core structure for the application of pluggable fuel assemblies and the improved health physical conditions for the application of a pneumatic transportation system of the neutron source.Most results of the experiments on it are to provide the designers of PWR for their reference.

本文介绍了我所铀水栅零功率实验装置的概貌,并简述了在该装置上开展的一些实验工作情况。

 
<< 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critical assembly的内容
在知识搜索中查有关critical assembly的内容
在数字搜索中查有关critical assembly的内容
在概念知识元中查有关critical assembly的内容
在学术趋势中查有关critical assembly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