核動力反應堆 的英文怎麼說

中文拼音 [hédònglìfǎnyīngduī]
核動力反應堆 英文
nuclear power reactor
  • 核 : 核構詞成分。
  • 力 : Ⅰ名1 （力量; 能力） power; strength; ability; capacity 2 [物理學] （改變物體運動狀態的作用） forc...
  • 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. Fuel assembly identification for nuclear power reactors

    核動力反應堆的燃料組件標識
  2. Corrosion of metals and alloys - aqueous corrosion testing of zirconium alloys for use in nuclear power reactors

    金屬和合金的腐蝕.核動力反應堆用鋯合金的耐水腐蝕試驗
  3. In - core temperature or primary envelope temperature measurements in nuclear power reactors. characteristics and test methods

    核動力反應堆中燃料芯體溫度或主包殼溫度測量.特性和試驗方法
  4. The carrier is capable of launching one aircraft every 20s. the nuclear - powered carrier has two general electric pressurized water reactors driving four turbines of 260, 000hp 194mw and four shafts. there are four emergency diesels of 10, 720hp

    尼米茲級航空母艦的動力來自兩部通用動力公司的壓水式核反應堆，由反應堆推動4個渦輪，從而產生26萬匹馬力合194兆瓦的動力來驅動4個槳軸，使航空母艦的速度可以超過30節。
  5. The reactor can be shutdown during emergency by cutting off the power supply to the control rod driving mechanism which then causes the control rods to drop down to the reactor core by gravity quickly and thereby stopping the nuclear fission immediately

    在需要緊急停堆時， ?須切斷控制棒驅動機械的電源，控制棒便會因地心吸力而快速下墜至反應堆堆芯，立即停止核裂變。
  6. The primary function of reactor protection system is to protect the integrity of the three nuclear safety barriers, namely, fuel cladding, primary pressure boundary and containment. when the certain safety limits, determined by the accident studies, are exceeded, the reactor protection system will give the protection signals of reactor trip and / or safeguard actuations, and then the reactor trip system and / or the engineered safety features are actuated

    反應堆保護系統的功能主要是保護三道核安全屏障（燃料包殼、一迴路壓力邊界和安全殼）的完整性，當運行參數達到危及三道屏障完整性的閾值時，保護系統動作觸發反應堆緊急停堆和啟動專設安全設施。
  7. Acquisition and documentation of reference power reactor physics measurements for nuclear analysis verification, guide for

    核分析鑒定用參考動力反應堆物理測量的數據獲得及文件編制指南
  8. 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。
  9. The forming - nucleus drive power could form numerous little crystal nucleus under natural melting temperature. the formation of tic particles in the melt could be divided into two phases which was forming - nucleus and growth. the forming mechanism of tic was : melting ti first surrounded c, then ti melting in the alloy and c formed a complicated reaction mesosphere on the carbon surface

    根據熱力學及動力學分析，認為在碳顆粒界面處tic的形核率很高，形核驅動力足以在正常的熔煉溫度下形成眾多的小晶核；熔體中tic顆粒的合成可分為形核與長大兩個階段，其形核機制為：首先活性ti原子包圍c ，溶入合金中的ti與c在碳表面形成一復雜反應中間層，隨著反應進行， ti和c顆粒不斷減少，生成的tic不斷彌散分佈於熔體中；其長大過程伴隨著tic顆粒的相互堆砌、聚集和形態規則化。
  10. On the other hand, quite a number of practical systems with numerous dimensions may have some fast variables taking on singular impulse characteristic, such as electric power system, control system of rolling mill assembly, biochemical process, nuclear reactor, control system of airplane and rocket, and chemical diffused reaction, etc. so, it is important to study the problem of robust control of singular system i n the domain of control theory

    一般這些不確定性並非不可度量的，通常能給出這些不確定性大小的某種約束，魯棒控制理論正是處理系統模型具有不確定性的有效方法。另一方面，在大多數維數很大的實際系統中，都有呈現奇異攝動特性的快變變量，如電力系統，冷軋機的工業控制系統，生物化學過程，核反應堆，飛機和火箭系統，以及化學擴散反應等。
  11. Positioning of moving table for checking screw holes of nuclear reactor pressure vessel

    核反應堆壓力殼螺栓孔檢測自動小車的定位
  12. 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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