测量了反应堆堆芯里的中子通量分布。
Neutron flux distributions in the reactor core are measured.
介绍了某池式研究堆中子通量分布测量及数据的计算机处理原理、方法、开发及工作情况。
The computer system of neutron distribution measurement and data processing in pool type reactor including its principle, method, design and work situation is described.
研究利用穿透概率法求解二维六角形轻水堆燃料组件内中子通量密度分布。
The paper describes the model for calculating the neutron flux density distribution in two dimensional hexagonal geometry assembly of light water reactor (LWR) by transmission probability method.
本文提出的中子掺杂硅单晶旋转辐照模型,给出了热中子通量在硅断面上的分布.平均值和不均匀度。
The rotating irradiation model for ND silicon presented in this paper gives distribution, mean value and heterogeneity of the thermal flux on the cross section of silicon.
讨论了用穿透概率法求解二维六角形几何轻水堆燃料组件中子通量的分布。
The flux distribution of two dimensional hexagonal geometry fuel assembly for LWR is studied, using the transmission probability method.
作者在MCNP的基础上,开发了中子测井,中子通量随能量、时间分布蒙特卡罗(MC)模拟软件包。
Based on MCNP, authors developed the software package of the Monte Carlo method to simulate the neutron flux distributions with the space, energy and time for neutron logging.
六角形节块内的中子通量密度分布采用高次多项式近似表示,最后导出通量矩方程及偏流的响应矩阵方程。应用粗网再平衡和渐近源外推方法加速收敛。
The nodal equations and response matrix equations are derived using higher order polynomial approximations to the spatial dependence of the flux within the hexagonal-z node.
六角形节块内的中子通量密度分布采用高次多项式近似表示,最后导出通量矩方程及偏流的响应矩阵方程。应用粗网再平衡和渐近源外推方法加速收敛。
The nodal equations and response matrix equations are derived using higher order polynomial approximations to the spatial dependence of the flux within the hexagonal-z node.
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