熱核堆 的英文怎麼說

中文拼音 [rèhéduī]
熱核堆 英文
fusion reactor
  • 核 : 核構詞成分。
  • 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...
  • 熱核 : thermonuclear
  1. A nuclear reactor generates prodigious amounts of heat.

    一座核反應堆能發出巨大的熱量。
  2. Bonus boling nuclear superheat reactor

    沸騰式過熱核反應堆
  3. Boiling nuclear superheat reactor

    核過熱沸騰反應堆
  4. Laser controlled thermonuclear reactor

    激光受控熱核反應堆
  5. The reactor protection system which we analyze this time is in broad sense. the analytical scope is from the systematic sensors ( thermodynamic instrumentation groups and nuclear instrumentation groups ) to the rod cluster control assemblies and the signals of engineered safety feature actuation system

    本次分析的rpr系統為廣義的反應堆保護系統，分析的范圍從系統的傳感器（熱工儀表和核儀表）到控制棒組件及專設安全設施驅動信號部分。
  6. Decay heat power in nuclear fuels of light water reactors ; non - recycled nuclear fuels

    輕水反應堆核燃料衰變熱功率的計算.不回燒的核燃料
  7. Decay heat power in nuclear fuels of light water reactors ; non - recycled nuclear fuels ; documentation and illustration

    輕水反應堆核燃料衰變熱功率的計算.不回燒的核燃料
  8. For years he was a “ hot reactor ”. on the exterior, he was cool, calm and collected, but on the interior, stress was killing him

    多年來，他一直是一個「熱核反應堆式的人」 。他那時表面上顯得冷靜，成穩和泰然自若，但內心深處的壓力正摧毀著他的生命。
  9. Decay heat power in nuclear fuels of high - temperature reactors with spherical fuel elements

    帶球形燃料元件的高溫反應堆的核燃料衰變熱力的計算
  10. Decay heat power in nuclear fuels of high - temperature reactors with spherical fuel elements ; documentation and illustration

    帶球狀燃料元件的高溫反應堆的核燃料衰變熱力的計算
  11. Zirconium alloys are employed extensively in light water cooled reactors ( lwr ) as the cladding materials of fuel elements and other structural materials because of the low capture cross - section for thermal neutrons, good resistance to water - side corrosion at elevated temperature, adequate mechanical properties and high thermal conductivity

    由於鋯的熱中子吸收截面小，並具有優異的耐高溫水腐蝕性能、良好的綜合力學性能和理想的熱導率，因此，鋯合金被用作核電站水冷動力堆核燃料元件的包殼材料和堆芯的其它結構材料。
  12. In the " nuclear island ", heat is produced by nuclear fission in the reactor and delivered by pressurised water in the

    核島內的反應堆會進行核裂變，並產生熱力，熱力由
  13. Preliminary neutronics design of the dual - cooled lithium lead blanket for fds - ii, jingjing li, shanliang zheng, et al., fusion engineering and design, 75 ? 79 ( 2005 ) 715 ? 719

    聚變發電反應堆雙冷鋰鉛包層熱工水力學設計與分析，汪衛華，劉松林，王紅艷等，核科學與工程， 2005 ， 25 （ 2 ） 163 - 168 。
  14. It was in this paper that the main research contents of nuclear heating and gain factor and its crux technology are affirmed for carr

    本文針對中國先進研究堆（ carr ）的冷中子源系統，研究並確定了冷中子源系統核發熱和冷中子增益的主要計算方法。
  15. Characteristic study of highly subcooled boiling in the 5 mw nuclear heating reactor

    核供熱堆高欠熱沸騰的特性研究
  16. 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。
  17. 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。
  18. Test investigation on sgtr of single tube break and three - tube break is carried out on hpitf of ciae to deeply understand the thermal - hydraulic behavior during pressurized - water - reactor ( pwr ) sgtr and to provide an integral data base for code assessment and development. the facility, a full height and 1 / 1000 - scale ( by volume ) of qinshan nuclear power plant, incorporates two identical loops with active pumps and steam generators ( sg ). the initial steady state of the test basically simulated that of the reference plant operation

    為了深入了解核電廠蒸汽發生器傳熱管破裂事故發生后的熱工水力現象，以及對壓水堆（ pwr ）核電廠系統分析程序進行分析和評價，在高壓綜合試驗裝置上開展了蒸汽發生器傳熱管破裂試驗研究高壓綜合試驗裝置以秦山核電廠主迴路系統為模擬對象，該裝置為雙環迴路系統，容積比為1 ： 1000 ，高度比為1 ： 1 。
  19. Nuclear design should make boiling water reactor power plant meet the safety criteria such as criteria for safety shutdown, after - heat removal and radioactive inclusive

    核設計應使沸水堆核電站滿足安全停堆準則、余熱導出準則、放射性包容準則等安全準則。
  20. Finally, it was compared and optimized for those basics that influence the heating and gain factor such as the position of cns vertical channel, the dimension of moderator cell and so on. all in all, this study can provide the calculating method, analyzing method, optimized ways and partial optimization for carr cns design and construction

    對同時影響核發熱和增益的因素（如：垂直孔道位置及冷包尺寸）進行了分析比較和優化，為carr堆冷中子源系統的設計和建造提供了計算方法、優化思路和部分優化結論。
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