水冷反應堆 的英文怎麼說

中文拼音 [shuǐlěngfǎnyīngduī]
水冷反應堆 英文
water cooled reactor
  • 水 : 名詞1 （由兩個氫原子和一個氧原子結合而成的液體） water 2 （河流） river 3 （指江、河、湖、海、洋...
  • 冷 : Ⅰ形容詞1 （溫度低; 感覺溫度低） cold:冷水 coldwater; 你冷不冷? do you feel cold?; are you feeling...
  • 反 : Ⅰ名詞1 （方向相背） reverse side 2 （造反） rebellion 3 （指反革命、反動派） counterrevolutionari...
  • 應 : 應動詞1 （回答） answer; respond to; echo 2 （滿足要求） comply with; grant 3 （順應; 適應） suit...
  • 堆 : Ⅰ動詞（堆積） pile up; heap up; stack Ⅱ名詞1 （堆積成的東西） heap; pile; stack 2 （小山 多用於地...
  1. Light water cooled graphite moderated reactor

    輕水冷卻石墨慢化反應堆
  2. Light water cooled heavy water reactor

    輕水冷卻重水反應堆
  3. Cooldown criteria for light water reactors

    輕水反應堆冷卻準則
  4. Auxiliary feedwater system for pressurized water reactors

    加壓水冷反應堆的輔助供水系統
  5. Nuclear power plants - pressurized water reactors - vibration monitoring of internal structures

    核電廠.加壓水冷反應堆.內部結構振動監測
  6. Standard guide for in - service annealing of light - water cooled nuclear reactor vessels

    輕水冷卻核反應堆容器在運轉中逐漸冷卻的標準指南
  7. 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
  8. A mathematic model of reactor, steam generator, pressurizer is developed based on characteristic of pwr coolant system. for reactor, the point reactor kinetics equation with six - group delayed neutrons is used and influence of coolant ' s and fuel ' s temperature is considered, conduction model of one dimension and single - channel model is used in thermal and hydraulic calculation, third - order hermite polynomial is used to solve the point reactor kinetics equation

    對于反應堆，在物理計算中採用了帶有六組緩發中子的點堆方程，同時考慮了多普勒效應及冷卻劑溫度效應對反應性的影響；在熱工水力計算中採用了一維的熱傳導模型與單通道模型；在求解點堆方程中採用了hermite插值的方法，克服了點堆方程的剛性問題。
  9. Preliminary neutronics design of the dual - cooled lithium lead blanket for fds - ii, jingjing li, shanliang zheng, et al., fusion engineering and design, 75 ? 79 ( 2005 ) 715 ? 719

    聚變發電反應堆雙冷鋰鉛包層熱工水力學設計與分析，汪衛華，劉松林，王紅艷等，核科學與工程， 2005 ， 25 （ 2 ） 163 - 168 。
  10. The water temperature at the reactor pressure vessel outlet is about 330 degree c whereas the water temperature at the inlet of the vessel is about 290 degree c. the cooling water is in a sub - cooled condition at such high temperature and pressure to prevent it from boiling

    反應堆出水的溫度約為攝氏330度，而入水口的溫度約攝氏290度。在這高溫及高壓狀態下的冷卻水會處于欠熱狀態即冷卻水的溫度與其沸點有一段距離，因此不會沸騰。
  11. 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。
  12. Measurements for monitoring adequate cooling within the core of pressurized light water reactors

    加壓輕水反應堆堆芯中適度冷卻的監測
  13. Condensation of steam in the presence of noncondensable gases is an important heat transfer mode in the passive containment cooling system ( pccs ). in the past decade, great efforts have been made on the investigation of this regime

    含有不凝性氣體的蒸汽冷凝是先進反應堆非能動安全殼冷卻系統（ pccs ）中重要的換熱方式，是當前核反應堆熱工水力學研究的一個熱點。
  14. Each primary coolant pump will circulate the cooling water ordinary water around the loop through the reactor core at a high pressure of about 155 bar 1 bar 100 kpa. in addition to its

    每一臺主泵會帶動約155巴1巴100千帕的高壓冷卻水普通水在其環路內經過反應堆堆芯循環流動，這些冷卻水不但是用作
  15. In addition, the fission rate in the pwr can also be controlled by adjusting the boron a neutron absorber concentration in the primary coolant circuit

    此外，壓水式反應堆的核裂變也可透過調節一迴路內冷卻劑中的硼濃度來控制硼亦是一種中子吸收體。
  16. In addition, the fission rate in the pwr can also be controlled by adjusting the boron ( a neutron absorber ) concentration in the primary coolant circuit

    此外，壓水式反應堆的核裂變也可透過調節一迴路內冷卻劑中的硼濃度來控制（硼亦是一種中子吸收體） 。
  17. 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
  18. In - service inspections for primary coolant circuit components of light water reactors - part 4 : visual inspection

    輕水反應堆初級冷卻劑迴路元件運行中檢查.第4部分:目
  19. In - service inspections for primary coolant circuit components of light water reactors - part 7 : radiographic testing

    輕水反應堆初級冷卻劑迴路元件運行中檢查.第7部分:放
  20. In - service inspections for primary coolant circuit components of light water reactors - part 1 : automated ultrasonic inspection

    輕水反應堆初級冷卻劑迴路元件運行中檢查.第1部分:自
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