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
   accident 在 核科学技术 分类中 的翻译结果: 查询用时:0.01秒
图标索引 在分类学科中查询
所有学科
核科学技术
安全科学与灾害防治
公路与水路运输
建筑科学与工程
电力工业
行政法及地方法制
矿业工程
公安
石油天然气工业
更多类别查询

图标索引 历史查询
 

accident
相关语句
  事故
    STUDY OF WATCH RUBY AS AN ACCIDENT DOSIMETER
    手表红宝石作为事故剂量计的研究
短句来源
    Calculation on Fission Product Transport and Release to Environment During PWR Accident
    压水堆事故工况下放射性裂变产物向环境转移和释放的理论计算
短句来源
    The Effect of TLD Badge Positions on Estimating Personnal Dose from r-ray External Irradiation Accident
    TLD佩戴位置对估算外照射事故个人剂量的影响
短句来源
    The Probability Analysis of the Critical Accident of the Fast Zero-Power Reactor
    快中子零功率反应堆(DF-VI)的临界事故概率分析
短句来源
    Experimental investigation on the quick estimation of personal dose in γ-ray external irradiation accident
    快速估算γ射线外照射事故个人剂量的实验研究
短句来源
更多       
  “accident”译为未确定词的双语例句
    The Measurements of the Dynamic State Thermal Parameters of HFETR Fuel Element:the Loss-of-Power Accident,the Shutdown Cooling and the Decay Heat Experiment
    高通量工程试验堆燃料元件动态热工参数测量——全厂断电、停堆冷却与剩余发热实验
短句来源
    Investigation on two-phase critical flow for loss-of-coolant accident of pressurized water reactor
    Investigation on two-phase critical flow for loss-of-coolant accident of pressurized water reactor
短句来源
    Considerations of Severe Accident in CPWR640 Nuclear Power Plant Design
    CPWR640核电站严重事故的考虑
短句来源
    Countermeasures of Advanced Reactor Severe Accident
    先进堆严重事故对策
短句来源
    Nonlinear Dynamic Response Analysis in Piping System for a Loss of Coolant Accident in Primary Loop of Pressurized Water Reactor
    压水堆主管道破裂工况下的非线性动力响应
短句来源
更多       
查询“accident”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。
  accident
The insurer designates the insurance premium and the insurance recovery that is paid to the client provided that the object was insured prior to the insured accident (failure).
      
If there is no penalty for nonconcluded contract (the insured accident occurs before conclusion of the contract), then the greater the ratio, the greater on the average the relative insurer's profit from the enterprise.
      
An analysis of correlations between cytogenetic indices in lymphocytes and levels of reduced glutathione in the plasma of peripheral blood in children born after the Chernobyl accident is presented.
      
Response of the glutathione system to chronic irradiation of human population after the Chernobyl accident
      
A complex relationship between glutathione level in plasma in human population (children living in radionuclide-contaminated regions and the Chernobyl liquidators) exposed to chronic low-level radiation after the Chernobyl accident was demonstrated.
      
更多          


The history of the development of irradiation research at home and abroad hasbeen retrospected in this paper.It is considered that the use of computer modellingin describing the irradiation behaviour of reactor materials is the principal featureof irradiation research today.In the field of irradiation techniques,the irradiationtests during power change and accident conditions have been emphasized.In themeantime of the development of the hot cell techniques,the development of irradia-tion measurement techniques...

The history of the development of irradiation research at home and abroad hasbeen retrospected in this paper.It is considered that the use of computer modellingin describing the irradiation behaviour of reactor materials is the principal featureof irradiation research today.In the field of irradiation techniques,the irradiationtests during power change and accident conditions have been emphasized.In themeantime of the development of the hot cell techniques,the development of irradia-tion measurement techniques on trial,the investigation of the sensitive elementswith short response time and the on-line data processing techniques of computerhave been paid a close attention.

本文回顾了国内外辐照研究的发展历史,认为用计算机模型描写反应堆材料辐照下的行为。是当前的主要特点。在辐照技术上,强调功率变化和事故工况下的辐照试验;在改进热室技术的同时,大力发展辐照中的测试技术;注意发展响应时间短的敏感元件及计算机的在线数据处理。

The authors had measured the transient of the thermal parameters(e.g.the inlet and outlet coolant temperature of fuel element case,the temperature offuel cladding,the flow of fuel element case and its thermal power)of the fuelelement at loss-of-power accident,the flow-reversal transient when emergencypump was starting and stopping during shutdown cooling,and the long-timedecay heat after shutdown by means of the in-core fuel element temperature-flowmeasurement facility of HFETR.The above-mentioned measurement...

The authors had measured the transient of the thermal parameters(e.g.the inlet and outlet coolant temperature of fuel element case,the temperature offuel cladding,the flow of fuel element case and its thermal power)of the fuelelement at loss-of-power accident,the flow-reversal transient when emergencypump was starting and stopping during shutdown cooling,and the long-timedecay heat after shutdown by means of the in-core fuel element temperature-flowmeasurement facility of HFETR.The above-mentioned measurement results havebeen described.

作者应用高通量工程试验堆堆芯燃料元件温度-流量测量装置测定了在全厂断电事故情况下的燃料元件热工参数(元件盒进出口水温,元件包壳温度,元件盒流量及其热功率)的瞬态过程,测定了在停堆冷却过程中启停事故泵时的流动反向过程,进行了停堆后的长时间剩余发热测量,给出了上述测量结果。

The rod ejection accident is the most serious one in the reactivity accidents.It is of the limiting accident,as is the large break LOCA.Although there is alittle probability of its occurence,the research results could directly be appliedto the control rod operatiog modes and could guide the safe operation of reactor.This paper analyzes the typical rod ejection accident in PWR by use of thepoint reactor kinetic model.The partial adiabatic approximation is adopted beca-use the whole accident...

The rod ejection accident is the most serious one in the reactivity accidents.It is of the limiting accident,as is the large break LOCA.Although there is alittle probability of its occurence,the research results could directly be appliedto the control rod operatiog modes and could guide the safe operation of reactor.This paper analyzes the typical rod ejection accident in PWR by use of thepoint reactor kinetic model.The partial adiabatic approximation is adopted beca-use the whole accident process takes a very short time.The resuelt of analysisshows that this approach is slightly conservative and the calculated power peak-ing is higher than the real value.

压水堆弹棒事故是反应性事故中最严重的事故,它和大破口失水事故一样,都属于极限事故。尽管这种事故的发生概率比较小,但其研究成果将直接用于控制棒运行方式的选择上,并指导反应堆的安全运行.本文是用点堆动力学模型对典型的压水堆进行弹捧事故分析.由于整个事故过程所需时间很短,我们采用了部分绝热近似.分析结果表明:这种方法是偏于保守的,计算出来的功率峰要比实测数值高一些.

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