nuclear reactor coolant 中文意思是什麼
nuclear reactor coolant
解釋
核反應堆冷卻劑-
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。 -
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。 -
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。 -
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。 -
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。 -
Nuclear reactor and primary coolant system
核反應堆及主冷卻劑系統 -
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。
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