nuclear reactor safety 中文意思是什麼

nuclear reactor safety 解釋
反應堆運轉安全性
  • nuclear : adj 1 核的，成核的；有核的。2 【物理學】原子核的；原子能的；原子彈的；核動力的。3 〈比喻〉核心的...
  • 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. 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》 。
  3. 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。
  4. 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
  5. 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
  6. 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
  7. 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。
  8. 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。
  9. 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。
  10. 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
  11. 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
  12. 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
  13. Nuclear design should make boiling water reactor power plant meet the safety criteria such as criteria for safety shutdown, after - heat removal and radioactive inclusive

    核設計應使沸水堆核電站滿足安全停堆準則、余熱導出準則、放射性包容準則等安全準則。
  14. In fact, the three codes are standard ones extensively used worldwide for decades in nuclear reactor engineering design, nuclear reactor radiation shielding safety analysis and other fields of nuclear energy research

    事實上，這三個程序是國際上近幾十年來在核反應堆工程設計、核反應堆輻射屏蔽安全分析等核能研究領域中廣泛應用的標準程序。
  15. Nuclear criticality safety for fissile materials outside reactor - basic technical criteria and subcritical limits for handling, processing and operations of fissile materials

    反應堆外易裂變材料的核臨界安全易裂變材料操作加工處理的基本技術準則與次臨界限值
  16. 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
  17. 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 。
  18. The whole concern in the nuclear energy development field is mainly focused on the study of the safety, efficiency and how to deal with nuclear radioactivity waste. almost all research is divided into two ways. the one way is to improve on those existed reactor for the better safety, the other is to carry on the fully new design for the best result

    在核能發展領域中，安全性、經濟性和放射性廢物的處理與處置問題始終是矛盾的關鍵，目前研究工作主要在兩個方向進行：一個方向是通過改進現有堆型的設計，另一個方向是進行創新設計。
  19. Considering the relationship between the phenomena of critical heat flux ( chf ) and the safety of nuclear reactor, the research of chf on experiment and theory has been carried in detail

    由於臨界熱流密度（ chf ）與反應堆安全密切相關，所以人們從實驗和理論上都已經對該現象進行了廣泛的研究。
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