核蒸汽發生器 的英文怎麼說

中文拼音 [hézhēngqìfāshēngqì]
核蒸汽發生器 英文
nuclear steam generator
  • 核 : 核構詞成分。
  • 蒸 : Ⅰ動詞1. （蒸發） evaporate2. （利用水蒸氣的熱力使食物熟或熱） steam Ⅱ名詞[中醫] （將藥物隔水蒸熟） steaming
  • 汽 : 名詞1. （由液體或某些固體變成的氣體） vapour2. （水蒸氣） steam
  • 發 : 名詞（頭發） hair
  • 生 : Ⅰ動詞1 （生育; 生殖） give birth to; bear 2 （出生） be born 3 （生長） grow 4 （生存; 活） live;...
  • 器 : 名詞1. （器具） implement; utensil; ware 2. （器官） organ 3. （度量; 才能） capacity; talent 4. （姓氏） a surname
  • 蒸汽 : vapour; reek; breath; steam蒸汽採暖 steam heating; 蒸汽錘 [機械工程] steam hammer; 蒸汽打樁鍾 ste...
  1. Nuclear power station with pressurised water reactor is basically divided into the " nuclear island " where steam is produced in the steam generator by nuclear power generated from a reactor, a " conventional island " where steam supplied from the nuclear island is used to drive the turbine - generator to produce electricity, and the balance of plant ( bop ) which consists of the station auxiliaries and ancillary plants, etc

    採用壓水式反應堆的核電站基本分為核島、常規島和核電站其他部分。由反應堆產生的核能會通過在核島內的蒸汽發生器產生蒸汽，而核島所供應的蒸汽會推動常規島內的渦輪發電機發電。核電站其他部分則包括站內的輔助設備及附屬設施等。
  2. Nuclear power station with pressurised water reactor is basically divided into the " nuclear island " where steam is produced in the steam generator by nuclear power generated from a reactor, a " conventional island " where steam supplied from the nuclear island is used to drive the turbine - generator to produce electricity, and the balance of plant which consists of the station auxiliaries and ancillary plants, etc

    採用壓水式反應堆的核電站基本分為核島常規島和核電站其他部分。由反應堆產生的核能會通過在核島內的蒸汽發生器產生蒸汽，而核島所供應的蒸汽會推動常規島內的渦輪發電機發電。核電站其他部分則包括站內的輔助設備及附屬設施等。
  3. Simulation and analysis on dynamics characteristic for nuclear steam generator water level process

    核動力蒸汽發生器水位動力學特性模擬與分析
  4. Develop and manufacture large pumped storage units, large tubular turbine units, high - power super - critical thermal power unit, large air - cooled turbine generator, large cfb boilers, high - power nuclear steam turbine and generator, pressure shell of nuclear island, high - pressure evaporator and primary pump

    開發生產大型抽水蓄能機組、大型貫流式機組、大功率超臨界火電機組、大型空冷汽輪發電機、大型循環硫化床鍋爐、大功率核電站汽輪機和發電機、核島設備壓力殼、高壓蒸發器和主泵等核電一級設備。
  5. This condensate discharge from the condensers feed water is pumped back to the steam generator in the nuclear island to be converted into steam again

    從冷凝器流出的凝結水即給水會泵回核島內的蒸汽發生器，然後再次轉化為蒸汽。
  6. This condensate discharge from the condensers ( feed water ) is pumped back to the steam generator in the nuclear island to be converted into steam again. cooling water for the condensers is taken from the sea via the seawater pumps in the pump house

    從冷凝器流出的凝結水（即給水）會泵回核島內的蒸汽發生器，然後再次轉化為蒸汽。在這過程中，蒸氣會將渦輪發電機作高速轉動（
  7. 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 。
  8. The break was assumed to be a single tube double - ended and three - tube double - ended shear break. the diameter of the break orifice is 0. 876mm and 1. 518mm respectively. the characteristic responses of main thermal - hydraulic parameters, such as primary pressure, secondary pressure, break flow rate, pressurizer level, secondary side level of steam generator and so on, were presented in this thesis

    試驗再現了核電廠蒸汽發生器單根傳熱管雙端斷裂事故和三根傳熱管雙端斷裂事故發生后的熱工水力現象，給出了事故過程中一次系統壓力、二次系統壓力、破口流量、蒸汽發生器二次側水位、穩壓器水位、元件表面溫度等主要參數的瞬態響應。
  9. 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。
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