water steam reactor 中文意思是什麼

water steam reactor 解釋
水-蒸汽反應堆
  • 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；...
  • steam : n 1 蒸汽，水蒸氣，水氣，霧，蒸氣壓力。2 〈口語〉精神，精力，氣力；怒氣。3 輪船，乘輪船旅行。vi 1 ...
  • 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. 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. Bwr is a light water reactor using ordinary water as coolant and moderator similar to the pwr except it only has a single circuit connecting the reactor and the turbine without a steam generator

    沸水式反應堆是輕水反應堆的一種，這種反應堆和壓水式反應堆相似，均利用普通水作為冷卻劑及慢化劑，但沸水式反應堆只有一個連接反應堆和渦輪機的迴路，且沒有裝設蒸汽發生器。
  4. Water in the reactor is kept at a lower pressure of about 75 bars such that it will boil at about 285 degree c. the steam produced from the reactor will directly feed into the turbine after passing through steam separators above the reactor core

    反應堆的水會維持約75巴的低壓，令水可以在大約攝氏285度時沸騰。反應堆所產生的蒸汽會經過堆芯上方的蒸汽分離器，然後直接送到渦輪機。
  5. 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 。
  6. Abstract : a thermo - economical diagnostic mathematical model for pressurizedwater reactor ( pwr ) nuclear cogeneration plant is proposed based on heat assignment method. this model simplifies the calculation of thermal system and can be used to calculate the index variations caused by heating steam parameters as temperature, return percentage and return place of the return water. some examples are given to show the usefulness of this model

    文摘:基於熱電聯產機組熱量法分配的特點，建立了熱電聯產壓水堆機組熱力系統發生變化對熱經濟性指標影響的計算模型，提出了供熱系統參數? ?供熱回水率、回水溫度、回水地點變化對壓水堆機組熱經濟性影響的定量診斷數學模型，可將復雜的熱力系統全面計算簡化成3個一次方程.通過實例計算，驗證了所提數學模型是正確可行的，同時具有概念清晰、計算簡捷的特點
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