fuel bundle
fuel bundle 双语例句
Engel`s work and CRT model, three semiempirical correlations ICRT were developed to calculate laminar, transition, and turbulent parallel flow pressure drop across wire-wrapped rods. With CRT model and the heat transfer coefficient WEST, reasonably accurate temperature distribution in a fuel subassembly was obtained by the improved subchannel analysis code SUPERENERGY. The results indicate lower coolant temperature and higher film temperature in internal regions. The code CFX was used to show the 3D flow field and temperature distribution in a rod bundle, and the numerical results show good agreement with CRT model, ICRT correlation and the improved SUPERENERGY code.
Engel等人工作的基础上，提出了ICRT压降关系式，用以计算冷却剂在湍流区、过渡流区和层流区的棒束压降；引入CRT模型和WEST对流传热模型，改进了SUPERENERGY子通道分析程序，并将改进程序与原程序计算结果进行了对比，结果表明：最热子通道出口温度略有降低，液膜温压略有增加；并用计算流体力学软件CFX对中国实验快堆单盒燃料组件活性段进行了三维数值模拟，将计算结果用CRT模型、ICRT压降关系式及改进后的SUPERENERGY子通道分析程序进行了验证，相互符合较好。
Increasingthe number of cluster fuel rods can lower the maximum linear power of fuel rod andthus improve thermal-hydraulics performance and safety margin of fuel bundle. The71-rods bundle is 1/7 symmetrical and has the same basic overall dimensions and fuelloading with CANFLEX fuel. The 71-rods bundle changes the number of rings from 4 to 5. The 61-rods is 1/6 symmetrical and has the same design rules with 71-rodsbundle. The power and burnup distribution of 61-rods are a little worse than those ofCANFLEX and 71-rods bundle.
增加棒束型燃料的元件棒数目，可以降低元件棒最大线功率密度、改善热工水力性能、加大安全裕度。71-rods燃料棒束组件采用和CANFLEX燃料组件完全一致的结构和燃料装量，元件棒排布采用1/7对称结构，将四圈燃料增加为五圈。61-rods棒束采用1/6对称结构，棒束的设计准则和71-rods相同。61-rods棒束的功率以及燃耗分布不如CANFLEX和71-rods棒束平坦。
The 3-D single phase simulation using CFX for the rod bundle channnel was going on by choosing the reasonable mathematical and physical models and boundary conditions. After a lot of numerical calculations, the sensitivity of gemotery was validated. The flow and heat transfer characteristics for several typical velocities were numerically analyzed and visually showed. The results show that the CFX simulation can be used for designing and optimizing fuel assembly in reactor engineering.
通过选定合理的数学、物理模型和边界条件，采用通用CFD程序ANSYS CFX 10.0对带有AGA-2G定位格架的5×5棒束通道流场进行了三维单相数值模拟，经过大量计算，验证了厚度、刚突等几何敏感性，得到了带定位格架棒束通道内的速度、压力和温度分布，分析了定位格架对流场、温度场的影响，直观地获得了搅混叶片的搅混效果，并将结果同实验值进行了初步比较。
This paper describes the basic problems of reactor core design of PWR such as chemical shimming reactivity, standardized non cassette fuel assembly, bundle of control rods, burnable poison, multi zone core and so on.
综合论述了压水堆堆芯设计中的化学补偿反应性、标准化无盒大型燃料组件、棒束型控制棒、可燃毒物和采用多区堆芯装料等基本问题。
Flow field measurements using LDA and numerical computation for rod bundle of reactor fuel assembly
反应堆燃料组件棒束流场的激光测试和计算
3-D Monte-Carlo method was employed for analyzing Liquid Metal Fast Breeder Reactor (LMFBR) sodium two-phase flow in fuel bundle under hypothetical loss of coolant accident (LOCA) conditions.
采用蒙特卡罗方法分析钠冷快堆在假想冷却剂丧失条件下燃料棒束的钠两相流传热。
On the turbulent mixing in reactor fuel bundle
关于反应堆元件棒束中的湍流交混
Experimental study on heat transfer properties of gas flow across the bundle tubes in cylindrical shell EXPERIMENTAL RESEARCH ON AUTOIGNITION OF FUEL INJECTED TRANSVERSELY INTO SUPERSONIC AIRSTREAM
气流横向冲刷圆壳管束换热试验研究超音速气流中横喷自点火的实验研究
Manufacturing process of CANDU-6 fuel Bundle for HWR nuclear power station
重水堆核电站用CANDU-6型燃料棒束的制造工艺
Three Dimensional Monte-Carlo Simulation Method for LMFBR Fuel Bundle Heat Transfer Under Loss of Coolant Accident Conditions
冷却剂丧失条件下钠冷快堆棒束传热的三维蒙特卡罗模拟方法
fuel bundle
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package: 指包装整齐严密的包裹或一包、一捆、一盒东西。
bundle: 指多件东西被捆扎在一起。
bunch: 指有规则地把同类东西固定在一起。
packet: 一般指小件行李、邮包、还可指更小一些的包。
pack: 指专为背负而包扎的包裹，也指驮物等。