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紧急停的英文

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"紧急停"怎么读用"紧急停"造句

英文翻译手机手机版

  • emergency outage
  • emergency shutdown mechanism
  • emergency stop

例句与用法

  • Emergency stop push button
    紧急停?按钮
  • Crash stopping distance
    紧急停?距离
  • Emergency shut - down
    紧急停
  • On april 26 , 1986 was mainly due to a combination of severe design deficiencies of the reactor and its shutdown system , coupled with violation of procedures when conducting an experiment on the reactor unit
    主要是由于反应堆及其紧急停堆系统在设计上存在严重缺陷,加上在反应堆进行实验时违反有关程序。由于
  • On april 26 , 1986 was mainly due to a combination of severe design deficiencies of the reactor and its shutdown system , coupled with violation of procedures when conducting an experiment on the reactor unit
    主要是由于反应堆及其紧急停堆系统在设计上存在严重缺陷,加上在反应堆进行实验时违反有关程序。由于
  • The reactor can be shutdown during emergency by cutting off the power supply to the control rod driving mechanism which then causes the control rods to drop down to the reactor core by gravity quickly and thereby stopping the nuclear fission immediately
    在需要紧急停堆时, ?须切断控制棒驱动机械的电源,控制棒便会因地心吸力而快速下坠至反应堆堆芯,立即停止核裂变。
  • A lot of papers about the report of probabilistic risk assessment of daya bay npp and system manuals has been read by the author and let as the basis . in this paper , based on the reliability analysis methods of failure mode and effect analysis and failure tree analysis , according to the result of event tree analysis of probabilistic risk assessment report of daya bay npp , the top events of the fault trees of reactor protection system and the success criteria were established . by using risk - spectrum procedure , the unavailability and the minimal cut - sets ( mcs ) of the fault trees were obtained
    本文在阅读了大量的大亚湾核电站pra报告和各种系统手册等资料的基础上,采用fmea (故障模式和影响分析)和fta (故障树分析)可靠性分析方法,依据大亚湾核电站pra事件树分析的结果,建立了以紧急停堆失效和专设安全设施驱动失效为顶事件的故障树,利用risk - spectrum程序,对所建的故障树进行定量分析,计算,得到系统故障树的失效概率和最小割集,从而为大亚湾核电站可视化风险分析软件提供数据支持。
  • The reactor protection system reliability analysis of daya bay npp is an important branch of the probabilistic risk assessment project of daya bay nuclear power plant . the purpose of probabilistic risk assessment of reducing reactor trip is to discover all the signals and the components which can result in reactor trip potentially , to assess the safety and reliability of systematic design , to find the potential design drawbacks and take effective measures to reduce such events
    大亚湾核电站反应堆保护系统是大亚湾核电站pra项目的重要的一个分支,大亚湾核电站减少紧急停堆pra (概率安全分析)是要找出各种可能引起机组紧急停堆的信号和部件,评价系统设计的安全性和可靠性,找到可能存在的设计缺陷,采取有效的防范措施,减少此类事件。
  • The primary function of reactor protection system is to protect the integrity of the three nuclear safety barriers , namely , fuel cladding , primary pressure boundary and containment . when the certain safety limits , determined by the accident studies , are exceeded , the reactor protection system will give the protection signals of reactor trip and / or safeguard actuations , and then the reactor trip system and / or the engineered safety features are actuated
    反应堆保护系统的功能主要是保护三道核安全屏障(燃料包壳、一回路压力边界和安全壳)的完整性,当运行参数达到危及三道屏障完整性的阈值时,保护系统动作触发反应堆紧急停堆和启动专设安全设施。
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