reactor coolant 中文意思是什麼

reactor coolant 解釋
反應堆冷卻劑
  • 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。
  • coolant : n. 【機械工程】冷卻劑；（減熱的）潤滑劑。
  1. Therefore, sequential research on chf is necessary. when in accidental conditions of nuclear reactor, the mass flux of coolant is very low. in such condition, the steam quality is high, and the mechanism of chf is mainly controlled by bulk flow, whereas microcosmic parameters near the chf area are affected by the flow conditions in whole tube which called " upstream memory effect "

    在反應堆事故工況下，冷卻劑流量很低，含汽量很高，其臨界機制與正常運行工況下的臨界機制有所不同，不僅是一種主流控制臨界工況，更由於其局部的各微觀參數受上游流道的累積效果的影響而存在上游記憶效應。
  2. Energy storage flywheel mounted in primary circulation pump of the reactor could supply coolant to the reactor core under power - off accident

    摘要核反應堆主循環泵上安裝儲能飛輪，能夠為反應堆在斷電事故下提供冷卻劑，避免堆芯損壞。
  3. As a important part of the nuclear power plant simulation, reactor coolant system simulation research is of great significance

    作為核動力裝置培訓模擬器的重要組成部分，冷卻劑系統的模擬計算研究具有很重要的意義。
  4. The reactor coolant system is an important system of nuclear power plant, so simulation of reactor coolant system is an important part of nuclear power plant simulation

    主冷卻劑系統是核動力裝置的一個重要系統，對主冷卻劑系統的模擬研究是核動力裝置模擬研究的一個重要部分，具有非常重要的意義。
  5. The type of reactor that will continue to dominate for at least two decades, probably longer, is the light - water reactor, which uses ordinary water ( as opposed to heavy water, containing deuterium ) as the coolant and moderator

    在未來起碼20年間（可能還要更久） ，輕水反應器將仍舊是主要的反應器類型，這種反應器以普通的水（而非含有氘的重水）來當做冷卻劑與緩和劑。
  6. 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。
  7. 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。
  8. Based on adequate survey to faults of sodium pump for the china experiment fast reactor, in order that the advanced diagnosis methods are used in the sodium pump which is under fabrication, different methods of fault diagnosis system of sodium pump are designed and programmed ; and the principal component analysis ( pca ) is used to fault diagnosis system of main coolant pump in a nuclear power station. the feasibility of fault diagnosis systems developed have been proved by simulation results

    本課題對中國實驗快堆鈉泵的故障進行了研究，把先進的診斷方法應用到正在製造中的鈉泵上，設計和開發了不同方法的鈉泵的故障診斷系統；同時也應用主元分析方法，建立了某核電廠的主冷卻劑泵的故障診斷系統，模擬實驗證明了以上三個系統的可行性。
  9. 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
  10. In order to adapt to real time simulation, the nodes of system and the predigestion was made according to the characteristic of reactor coolant system which will be simulated

    本論文針對要模擬的冷卻劑系統的特點，對系統進行了節點劃分，並做了適當簡化，以使其適應實時模擬的需要。
  11. In order to meet the needs for measuring the coolant water flow rate in - core of a nuclear heating reactor, two types of turbine flow meter with low rotation speed have been developed in our institute

    為適應核反應堆堆芯冷卻劑流量測量的需要，開發研製了新型低速渦輪流量變送器，按流量信號輸出不同，分別為磁感應模擬信號輸出和數字開關量輸出低速渦輪流量變送器。
  12. Liquid metal coolant reactor

    液態金屬冷卻反應堆
  13. Nuclear reactor and primary coolant system

    核反應堆及主冷卻劑系統
  14. In the thesis, the relap5 code is made use of simulating and calculating the passive core makeup tank ( cmt ) of the next generation reactor ac - 600 of our country. and the calculative results based on the comparative character of the system are compared with the experimental results in the corresponding experimental devices of ac - 600 makeup water tank in nuclear power institute of china ( npic ). finally the thesis conclusion summarized is that the makeup water passively injected to the reactor coolant system by the core makeup tank depending on the gravity is viable in the middle and small locas

    本論文利用relap5程序對我國下一代先進堆ac - 600的一個具有非能動性能的堆芯補水箱分系統進行了模擬計算，根據系統之間的可比性，把計算的結果和與之相對應的中國核動力研究設計院堆芯補水箱補水實驗裝置的實驗結果進行了定性的比較分析，得到了論文的結論：在中、小破口失水事故的工況下，堆芯補水箱依靠重力向反應堆冷卻劑系統實現非能動的補水是可行的。
  15. The primary coolant system of a 900 mw class reactor consists of the reactor pressure vessel and the primary circuit with 3 identical loop top figure

    一個900兆瓦的反應堆主冷卻劑系統上圖是由壓力殼及三個相同的環路相連組成即一迴路。
  16. The primary coolant system of a 900 mw class reactor consists of the reactor pressure vessel and the primary circuit with 3 identical loop ( top figure )

    一個900兆瓦的反應堆主冷卻劑系統（上圖）是由壓力殼及三個相同的環路相連組成（即一迴路） 。
  17. E standard practice for calculation of average energy per disintegration for a mixture of radionuclides in reactor coolant

    反應堆冷卻劑中放射性核素混合物每次蛻變的平均能量
  18. Rbmk is a type of pressure tube reactor designed in the former soviet union, which uses ordinary boiling water as the coolant and graphite as the moderator

    Rbmk是前蘇聯設計的一種以普通沸水為冷卻劑以石墨為慢化劑的壓力管式反應堆。
  19. 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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