reactor coolant system 中文意思是什麼

reactor coolant system 解釋
反應堆冷卻劑系統
  • 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。
  • system : n 1 體系，系統；分類法；組織；設備，裝置。2 方式；方法；作業方法。3 制度；主義。4 次序，規律。5 ...
  1. 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。
  2. 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。
  3. 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。
  4. 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。
  5. 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。
  6. Nuclear reactor and primary coolant system

    核反應堆及主冷卻劑系統
  7. 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。
  8. 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。
  9. 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） 。
  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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