pressurized-water reactor 中文意思是什麼

pressurized-water reactor 解釋
壓力水冷反應堆
  • pressurized : 承受余壓的
  • water : n 1 水；雨水；露；〈常作 pl 〉 礦泉，溫泉；藥水。2 〈常 pl 〉水體；水域；水道；海；湖；河；海域；...
  • 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. Burnable poison pressurized water reactor

    可燃毒物壓水反應堆
  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. Test investigation on sgtr of single tube break and three - tube break is carried out on hpitf of ciae to deeply understand the thermal - hydraulic behavior during pressurized - water - reactor ( pwr ) sgtr and to provide an integral data base for code assessment and development. the facility, a full height and 1 / 1000 - scale ( by volume ) of qinshan nuclear power plant, incorporates two identical loops with active pumps and steam generators ( sg ). the initial steady state of the test basically simulated that of the reference plant operation

    為了深入了解核電廠蒸汽發生器傳熱管破裂事故發生后的熱工水力現象，以及對壓水堆（ pwr ）核電廠系統分析程序進行分析和評價，在高壓綜合試驗裝置上開展了蒸汽發生器傳熱管破裂試驗研究高壓綜合試驗裝置以秦山核電廠主迴路系統為模擬對象，該裝置為雙環迴路系統，容積比為1 ： 1000 ，高度比為1 ： 1 。
  5. Criteria for nuclear reactor instrumentation - part 2 : pressurized water reactors

    核反應堆儀表準則第2部分:壓水堆
  6. 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」 。
  7. Classification for the items of pressurized water reactor nuclear power plants

    壓水堆核電廠物項分級
  8. Large pressurized water reactor

    大型壓水堆
  9. Pressurized water reactor pressure vessel - the principle of selecting materials and the basic requirements of the materials

    壓水堆壓力容器選材原則與基本要求
  10. In this paper, the method for transient characteristic calculation of pwr ( pressurized water reactor ) coolant system is studied and a model is developed

    本文根據壓水堆冷卻劑系統的特點，對反應堆、蒸汽發生器、穩壓器分別建立各自獨立的模型。
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