design of nuclear reactor 中文意思是什麼

design of nuclear reactor 解釋
核反應堆設計
  • design : vt 1 計劃，企圖，立意要…。2 指定，預定；留給，留著。3 設計，草擬，擬定，籌劃；起草，畫草圖，打（...
  • of : OF ＝Old French 古法語。
  • 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。
  1. Terms and definitions of nuclear technology - part 2 : reactor design

    核技術術語定義.第2部分:反應堆設計
  2. 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。
  3. Nuclear reactor instrumentation - pressurized water reactor of vver design - monitoring adequate cooling within the core during shutdown

    核反應堆儀器儀表. vver設計的壓水反應堆.在定堆期間監測堆芯的充分冷卻
  4. The burn up calculation is the important part of the study on the conceptual design of nuclear reactor

    在研究核反應堆的概念設計上，燃耗計算是一個重要的步驟。
  5. 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。
  6. In order to make the design process for power control system of experimental nuclear reactor optimal, objective and analytical, an analytical design process which contains the model linearization, model reduction, theoretical design of pid controllers is discussed

    摘要通過對實驗反應堆系統模型進行線性化和模型降階、再對降階模型進行pid控制器的理論設計的方法，可使反應堆功率調節系統的設計最優化、客觀化和解析化。
  7. The pressure container for the nuclear reactor pile which is introduced by this essay is designed and made by certain group company. it ' s a huge equipment used in the nuclear power station. the equipment is made up of two parts, a pressure container body and a lid. this paper is going to give the descriptions of the transport program design of the pressure container body. the body of the pressure container is 5. 165m wide, 4. 85m high and its net weight is 160t, because it is a large item for transporting in nature, the container needs a stern transporting condition. if we want to transport the container designedly and procedurely, to achieve no damage and no loss in the whole process, we must pay a careful investigation and find a feasible way to carry it

    該設備由壓力殼筒體和頂蓋兩部分組成，在此僅敘述核反應堆壓力殼筒體的運輸方案設計。核反應堆壓力殼筒體凈重160t ，寬5 . 165m ，高4 . 85m ，屬大件運輸。運輸技術條件要求極為嚴格，為使該大件運輸能有計劃、有步驟進行，確保整個運輸過程完整無損、萬無一失，必須進行深入細致的調查研究，尋找大件運輸的可行方案。
  8. Standard practice for design of surveillance programs for light - water moderated nuclear power reactor vessels

    輕水冷卻核反應堆容器的監督程序設計的標準操作規程
  9. 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。
  10. 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。
  11. Major : material science postgraduate : zhou xuchang advisor : zeng guangting huo yongzhong as a new type of shape memory alloy pipe coupling, nitinb pipe coupling has a good prospects on the connecting pipe. the study on the strength of nitinb connnetor system and design to optimize its structure have great meaning to its application on the connecting pipe of the steam maker in nuclear reactor on naval vessels

    Nitinb管接頭是一種新型形狀記憶合金管接頭，在管路連接上有著良好的應用前景。研究管接頭系統的強度並對其結構優化設計對它在艦艇核反應堆蒸汽發生器的管路連接上的應用有著重要的意義。
  12. The theme comes from the project the program development for transient sealing in reactor pressure vessel. this project is the subproject of the research project commissioned by the technical industry committee, department of defense, which is about the advanced reactor design in advanced pressurized water reactor nuclear power station

    本論文來源於國防科學技術工業委員會關于先進壓水堆核電站先進反應堆設計技術研究項目（批文號：科工委[ 1999 ] 149號）的子課題「反應堆壓力容器瞬態密封程序研製」 。
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