模擬反應堆 的英文怎麼說

中文拼音 [mónǐfǎnyīngduī]
模擬反應堆 英文
mock ureactor
  • 模 : 模名詞1. （模子） mould; pattern; matrix 2. （姓氏） a surname
  • 擬 : 動詞1. （設計; 起草） draw up; draft 2. （打算; 想要） intend; plan 3. （模仿） imitate
  • 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...
  • 模擬 : imitate; simulate; analog; analogy; imitation; simulation模擬艙 boilerplate; 模擬電路 [電學] circ...
  1. Consisting of the protracting graph of hydrogen - like atom ' s angle distributing, computer simulation of the symmetry of molecular orbital and chemical reaction mechanism, showing the molecular point group and symmetry element, computer simulation of molecular vibration, bravias ' s crystal lattice and their transforming, extracting of plane periodic lattice, extracting of solid periodic lattice, close packing of isometrical pellet and the structure of simple mental substance, close packing of unequal pellet and crystal structure of representative ionic crystal, computer simulation of phase analysis by x - ray diffraction

    內容包括類氫原子角度分布圖的繪制，分子軌道對稱性和反應機理的微機模擬，分子點群和對稱元素顯示，分子振動運動的微機模擬，布拉維晶格和晶格轉化，平面點陣抽取，立體點陣抽取，等徑網球的密堆積和金屬單質結構，不等徑圓球密堆積和典型離子晶體結構， x射線多晶衍射的微機模擬十個子模塊。
  2. The simulation of reactor physics and nuclear power plant system running using person - computer help for students studying the nuclear engineering course as well as the workers of nuclear power plant training

    用計算機對反應堆物理及核電站系統運行進行模擬，既有助於核工程專業的學生專業課的學習，也適合核電人員的初步培訓。
  3. Simulation study of internal model control system of refrigerant average temperature of nuclear reactor

    核電站反應堆冷卻劑平均溫度內模控制系統模擬
  4. In order to mix the esd with other methods, this paper explains esd / ft and esd / m methods, which increase the flexibility of the esd modeling. focusing on solving the dynamic pra problem, this article invents analytical / semi - analytical quantification of esds. finally, an accidental transient of fast reactor is studied

    國防科學技術大學研究生院學位論文最後，本文運用改進的esd方法並結合蒙特卡羅模擬對快中子反應堆系統潛在事故過程進行了動態概率風險評價，該應用研究展示了改進的esd方法在研究動態pra問題中所具有的巨大優勢。
  5. The wavelet packet analysis applied in fault diagnosis system is studied in this thesis. using simulation fault data, uncalm and time difference vibration signal of sodium pump are decomposed on different levels and frequencies. to picked - up the eigenvectors reflecting different fault of sodium pump with availability, simulation results have shown its satisfaction in the identification

    對小波包分析應用於故障診斷進行了研究，利用模擬出來的故障數據，將快堆鈉泵非平穩時變振動信號分解到不同層次和不同頻帶上，有效地提取出反映鈉泵不同故障（狀態）的特徵向量，在識別中得到了滿意的結果。
  6. The program fearpv is applied to analysis the sealing structure of the pressure vessel model during the total process, including bolt pretensioning process, heating and compression process, thermostated heating and constant pressure process, and the cooling and decompressing process

    應用反應堆壓力容器瞬態密封有限元分析程序對反應堆壓力容器模擬體密封結構進行了螺栓預緊、升溫升壓、恆溫恆壓、降溫降壓等全過程分析。
  7. The program fearpv is applied to 3 - d transient sealing analysis of nuclear pressure vessel during the total process, including bolt pretensioning process, heating and compression process, thermostated heating and constant pressure process, and the cooling and decompressing process. according to the analysis and computational results in this thesis, although the actual structure and work conditions of the pressure vessel in nuclear power station are much more complex than that of the pressure vessel model, the program fearpv still can get quite good convergence on the plasticity and

    由本文分析計算可知，雖然電站核壓力容器的結構及計算工況較壓力容器模擬體復雜得多，然而反應堆壓力容器瞬態密封有限元分析程序對塑性迭代和接觸迭代仍具有很好的收斂性，數值穩定性好，得到的結果具有良好的規律性，在升溫、升壓、恆溫、恆壓、降溫和降壓等過程中其規律和壓力容器模擬體基本相似。
  8. 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。
  9. In this thesis, radiation monitoring system ( rms ) real time simulation for the simulator of nuclear power plant is studied

    本論文的研究內容為核電廠反應堆輻射監測系統實時模擬。
  10. 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。
  11. Rms is a distinctive system in npp. so it is of great significance for npp operators training to fulfill rms simulation

    反應堆輻射監測系統是核電廠特有的系統，實現其模擬對培訓核電廠運行人員具有十分重要的意義。
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