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   堆芯 在 电力工业 分类中 的翻译结果: 查询用时:0.032秒
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堆芯
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  core
On the non-compactness of the core of nonatomic convexσ-continuous measure games
      
This paper concerns with the core of nonatomic games of form f(μ), whereμ is a nonatomic nonnegative measure and f is a continuous convex function on the domain ofμ.
      
The main result of this paper is that the core of the game is not compact under the norm topology unless the game itself is a measure.
      
This shows the largeness of the core in a sense other than that defined by Sharky for finite cases.
      
For example, in water, PCL and PAA formed core-shell nanospheres due to interpolymer hydrogen bonding.
      
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  reactor core
A new supercritical water-cooled reactor (SCWR) core structure (the mixed reactor core) and a new fuel assembly design (two-rows FA) are proposed.
      
By simulating the whole reactor core, the detailed mass flow distribution in the core was obtained.
      
The possibility is discussed of using the obtained data in simulating emergency conditions in the reactor core.
      
The interaction of nuclear reactor core melt with oxide sacrificial material of localization device for a nuclear power plant wi
      
The neutron spectrum at the center of the reactor core was measured by the neutron activation method using the a priori spectrum as a superposition of partial fission and evaporation spectra.
      
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Linear Programming (LP) method is used to search for PWR optimized fuel assemblyloading pattern. The objective function of the optimization is to minimize assembly power Peaking factor. A program code ALPOT based on the theory has been successfully used in Guangdong NPP (GNP-1) cycle 2 reload core design. The radial assembly averaged power peakingfactor decreases from 1. 33 to 1. 26, while the CPU times on ELXSI-6400 is only 300 odd seconds.

利用线性规划方法寻找PWR最优的燃料装载布置,目标函数为堆芯组件功率峰因子最小.将编制的计算程序ALPOT应用于大亚湾核电站(GNP-1)首次堆芯换料设计优化计算中,组件平均功率峰因子由原来的1.33降到1.26,在ELXSI-6400机器上花费CPU300多秒.

Solving dynamics equations of plasma in fusion-fission hybrid reactor core is performed by using Runge-kutta method .Taking different step-length at different time segment is used through computation which can ensure the solution accuracy and save CPU time. There obtained solution curves fully display burning process of plasma in reactor core. In addition, value feedack control method applies to optimization and control of solution curves.

用四阶龙格-库塔方法求解聚变-裂变混合反应堆堆芯等离子体动力学方程组,求解过程采用分段步长法,既可保证求解精度又可节省机时,所得出的解的曲线能充分反映堆芯等离子体的燃烧过程.求解过程还引用数值反馈控制方法用以对解曲线的优化和控制。这种数值反馈控制方法可以在工程技术上用来探索堆芯等离子体燃烧过程的控制。

The calculating method of temperature coefficient of reactivity for NHRs ispresented in this paper. An example case has been made for 200MW heating reactor.The fuel and moderator temperature coefficients were calculated for initial -- loaded coreand for the first cycle. The results provide a basis for the reactor safety analysis.

本文介绍了供热堆反应性温度系数的计算方法,以200MW堆为设计实例,计算了初装堆芯的燃料温度系数和慢化剂温度系数。同时,对于首炉运行工况下的温度系数作了比较细致的计算,这些计算结果为低温堆物理设计提供了科学依据。

 
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