reactor safety 中文意思是什麼

reactor safety 解釋
反應堆安全
  • reactor : n. 1. 反應者，被試驗者；【醫學】有（陽性）反應的人[動物]。2. 【電學】礙圈，扼流圈；電抗器；【化學】反應器；【物理學】反應堆。
  • safety : n. 1. 安全；平安，穩安，保險。2. （槍等的）保險器，安全瓣；〈口語〉低座腳踏車[自行車] （＝safety-bicycle）。3. 安全設備，保險裝置。4. 【棒球】安全打。
  1. General safety principles of nuclear reactor protection system

    核反應堆保護系統安全準則
  2. Series reactor is applied to ac power system with rated voltage of 6kv - 63kv and series connected with shunt capacitor banks for restraining wave distortion in grid voltage so as to improving the quality of power system and ensure the safety of its operation. it can restrain harmonic current and surge current in capacitor banks so that the capacitor will operate reliably

    Ckdk型串聯電抗器，適用於6 63 kv電力系統中，與並聯電容器相串聯，用以抑制電網電壓波形畸變，從而改變電網質量和保證電力系統安全運行抑制流過電容器組的諧波電流和限制合閘涌流，從而保護電容器的安全可靠運行。
  3. Dry - type air - cored series reactor is applied to ac power sys - tem with rated voltage of 6kv 10kv 35kv and series connected with shunt capacitor banks for restraining wave distortion in grid voltage so as to improving the quality of power system and ensure the safety of its operation

    乾式空芯串聯電抗器適用於6kv 10kv 35kv電力系統中與並聯電容器組串聯，用於抑制電網電壓波形畸變，從而改善電網質量和保證電力系統安全運行，抑制流過電容器組的諧波電流和限制合閘涌流，從而保護電容器使之安全運行。
  4. Both countries signed a memorandum of cooperation on nuclear safety for the westinghouse ap1000 nuclear reactor

    兩國簽署《美國核管制委員會和中國國家核安全局關于ap1000型核電機組核安全合作諒解備忘錄》 。
  5. The reactor protection system which we analyze this time is in broad sense. the analytical scope is from the systematic sensors ( thermodynamic instrumentation groups and nuclear instrumentation groups ) to the rod cluster control assemblies and the signals of engineered safety feature actuation system

    本次分析的rpr系統為廣義的反應堆保護系統，分析的范圍從系統的傳感器（熱工儀表和核儀表）到控制棒組件及專設安全設施驅動信號部分。
  6. Nuclear criticality safety for fissile materials outside reactor. performance and testing requirements for nuclear criticality detection and alarm systems

    反應堆外易裂變材料的核臨界安全核臨界事故探測與報警系統的性能及檢驗要求
  7. By using the method of fault tree analysis, this paper analyses the causes of fire and explosion of catalying & cracking reactor and regeneration, draws the fault trees of fire and explosion accidents of catalyzing & cracking reactor and regeneration respectively, calculates the structure importance, makes the structure importance arrangement according to the structure importance and the least path set, puts forward the prevention measures, and provides the reliable theoretical basis for the safety control of enterprises

    摘要應用故障樹分析方法，對催化裂化反應器和催化裂化再生器發生火災（爆炸）事故的原因進行分析，分別畫出催化裂化反應器和催化裂化再生器發生火災（爆炸）事故的故障樹，得出最小徑集合，並計算其結構重要度，根據得出的最小徑集合及其結構重要度進行排序，提出預防措施，為企業的安全管理提供了可靠的理論依據。
  8. Nuclear criticality safety for fissile materials outside reactor - borosilicate glass raschig rings and its application criteria

    反應堆外易裂變材料的核臨界安全硼硅酸鹽玻璃拉希環及其應用準則
  9. Nuclear criticality safety for fissile materials outside reactor nuclear criticality safety based on limiting and controlling moderators

    反應堆外易裂變材料的核臨界安全基於限制和控制慢化劑的核臨界安全
  10. The aim of this research project is to supply the technical preparation for the nuclear power station domestalization and autonomous design, to improve the design quality and level, to ensure the reliability of the sealing system in the advanced pressurized water reactor vessel, to ensure the nuclear safety, and to raise the design software level of the nuclear vessel sealing system to the advanced world class

    本課題研究的目的是為核電站國產化及自主設計提供技術準備，提高設計質量和設計水平，確保先進壓水堆核容器密封系統設計的可靠性，確保核安全，使核容器密封設計軟體達到世界先進水平。
  11. 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

    大亞灣核電站反應堆保護系統是大亞灣核電站pra項目的重要的一個分支，大亞灣核電站減少緊急停堆pra （概率安全分析）是要找出各種可能引起機組緊急停堆的信號和部件，評價系統設計的安全性和可靠性，找到可能存在的設計缺陷，採取有效的防範措施，減少此類事件。
  12. 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

    反應堆保護系統的功能主要是保護三道核安全屏障（燃料包殼、一迴路壓力邊界和安全殼）的完整性，當運行參數達到危及三道屏障完整性的閾值時，保護系統動作觸發反應堆緊急停堆和啟動專設安全設施。
  13. Nuclear criticality safety for fissile materials outside reactor - nuclear criticality safety criteria for steel - pipe intersections containing aqueous solutions of fissile material

    反應堆外易裂變材料的核臨界安全含易裂變物質水溶液的鋼質管道交接的核臨界安全準則
  14. Nuclear reactor use of the protection system for non - safety purpose

    核反應堆保護系統用於非安全目的準則
  15. Reactor protection system and monitoring equipment of the safety system

    反應堆安全系統的保護系統及監控設備
  16. Safety logic assemblies of nuclear reactor characteristics and test methods

    核反應堆安全邏輯裝置特性和檢驗方法
  17. Safety injection system - used to inject borated water into the reactor

    安全注入系統-把硼酸溶液注入反應堆
  18. Locks at reactor safety containments of nuclear power plants ; material locks, safety requirements

    核電廠反應堆安全殼上的閘.材料進出閘.安全要求
  19. In order to promote the development of china ' s nuclear power construction, in the early 1980s, china acquired gratis from the iaea the dot3. 5 code for calculating nuclear reactor safety

    為了促進中國核電建設的發展，中國早在80年代初期就從國際原子能機構無償獲得用於計算反應堆安全的計算機軟體程序dot3 . 5 。
  20. Application of the single failure criterion for light water reactor safety - related fluid systems

    輕水反應堆有關安全的液體系統的單一故障準則應用
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