此公式高度地反映了所有原子核内质子和中子分布的整数规律。
Above formula highly reflect the integer law of protons and neutrons distributing in all kinds of atomic nuclei.
详细研究了亲近势标度，发现用中子皮及中子分布弥散度的变化能较好地解释中子过剩自由度对亲近势标度偏离的影响。
It is found that the neutron skin and the neutron distribution diffusion can explam the influence of the neutron excess degree of freedom on the proximity scaling.
在这种情况下，如果采用扩散理论计算这种组件内的中子分布，会引起相当大的误差，但蒙特卡罗方法是非常适合于处理这种情况的。
To calculate the neutron distribution, in this case, a rather big errors would occur if the diffusion theory be used. However, Monte Carlo Method is suitable at dealing with the problem.
一个撞击铀235原子的中子，释放出一些γ，和一些中子，创造出2个裂变碎片,那它们自己会有出现的分布。
A neutron striking a uranium 235 atom, releasing some gammas and some neutrons, creating two fission fragments which themselves have a distribution of occurrence.
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.
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.
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.
利用中子活化分析技术测定了玻璃苗不同部位中的多种元素含量和分布状况及变化。
Meanwhile the variation and status of distribution of many elements content in the different parts of vitreous shoot were determined by neutron activation analysis technique.
计算和对比了使用聚焦单色器和平板单色器的强度增益和样品位置处的中子强度分布。
The intensity gains comparing to flat monochromator and the neutron intensity distribution at sample position were also given.
在软件模型的基础上分别计算了不同能量的中子进行治疗时的肿瘤及正常组织剂量分布，并对计算结果进行了分析。
The neutron absorbed dose rate distributions for tumour and natural histiocyte are calculated respectively based on this software and the results are analyzed.
测量了角响应、径向微分响应、能量响应及球腔内中子计数率分布，并估算了有效中心。
The angular response, the radial differential response, the energy response and the distribution of neutron counting rate inside sphere cavity are measured, and the effective centre is estimated.
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.
在不同实验系统上，测量了铁球壳表面不同位置上中子引起的绝对裂变反应率分布。
In different experiment systems, absolute fission reaction rates, derived from reflection neutrons, at different positions of the surface of an iron spherical shell were measured.
该系统计算的中子在方型混凝土管中的剂量率分布与实验结果符合得较好。
The dose rate distributions calculated with RSCAM in square concrete duct agree well with experiments.
本文叙述了用裂变径迹法测量强中子发生器中子注量分布的方法。
A measurement method of neutron fluence distribution for intensive beam generators based on the fission tracks was described.
并且给出角分布和次级中子能谱。
Angular distributions and energy spectra of secondary neutron are also given.
此解的中子密度空间分布曲率是随堆功率变化的，因此它比点堆模型方程的解析解精确。
The space curvature of neutron density of this solution is changed according to the changes of reactor power, so it is more precise than the analytic solution of point reactor model.
天文学家们将对脉冲星以及中子星，这一超新星爆炸后的残留物的分布信息感兴趣。我们当前的理解是否正确？
Astronomers will be interested in the new information regarding the population of pulsars, and hence neutron stars, as remains of supernova explosions.
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.
计算结果表明，脉冲引发时刻概率分布的计算结果与实验结果符合较好，所获得的缓发中子发射率规律可合理解释引发时刻概率分布的实验结果。
The result of initiation time is consistent with experiment. Emission rate of delayed neutron attained from calculation can well explain the probability distribution of initiation time.
中子衍射方法可以用来测量材料内部的三维残余应力分布，是一种重要的无损检测分析手段。
Neutron diffraction, an important non-destructive testing method, can facilitate 3-d mapping of residual stress in a bulk component.
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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