Neutron flux distributions in the reactor core are measured.
测量了反应堆堆芯里的中子通量分布。
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.
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。
First, the neutron diffusion equation is converted to three coupled one dimensional partial flux equation through transverse integration.
首先通过横向积分将中子扩散方程化为三个互相耦合的一维偏通量方程。
According to the nonlinear dynamic model of a nuclear reactor, a new constant neutron flux density control method based on nonlinear state feedback is presented.
针对核反应堆点堆动态非线性模型，提出了一种非线性状态反馈的中子通量密度恒值控制的新方法。
In the miniature neutron source reactor (MNSR) reactivity and neutron flux are related.
微型中子源反应堆的反应性和中于通量密度有一定的关系。
A coarse mesh method, in which the theory of nodal Green's function method is adopted, is applied to get the adjoint neutron flux, after a transformation of adjoint flux equations has been made.
将中子伴随通量方程变换处理以后，利用格林函数节块法的原理求解中子伴随通量，以此代替过去采用最多的细网有限差分法。
The intermediate and fast neutron flux spectrum in the core of the swimming-pool reactor is measured by multiple foil activation method.
用活化箔技术测定游泳池反应堆内中能中子与快中子通量谱。
A method is presented for the measurement of integrated thermal neutron flux in a high flux reactor by a Co-activation method.
本文叙述了用钴活化法测定高通量堆中热中子积分通量的方法。
The neutron measurement system based on the Nuclear Pumped Laser (NPL) techniques was explored in this work utilizing the relationship between the neutron flux and the NPL laser power.
利用核泵浦激光强度与入射中子注量率的相关性，探讨了反应堆活性区核泵浦激光中子探测器的理论可行性。
With MCNP/4B code, the influence of cut-off energy, flux tallies, nuclear databases and perturbation on the reaction rates calculation with neutron-activation method are analysed.
用MCNP／4B程序，对核活化法反应计算中的截断能量、通量计数方式、数据库、阈探测器之间的扰动等因素的影响作了分析。
The effect of low temperature on imaging speed of films for low flux neutron radiography has been studied experimentally. The optimum temperature for the neutron radiography is given.
本文研究了低温对低通量密度中子照像速度的影响，得出了低温照像的最佳温度值；
The neutron flux of reactor center port-hole is one of the important parameters for applications.
反应堆中央孔道中子注量值是反应堆的重要指标，也是反应堆应用的重要参数。
This paper proposes the flux mapping method using the higher order harmonics of the neutron equation.
提出用中子方程的高阶谐波进行通量拟合的方法。
The origins of natural neutron flux on the air-ground interface are described in this paper.
本文论述了地-空界面上天然宇宙中子流的来源；
A xenon poison method is proposed for measurement of thermal neutron flux density.
文章提出用氙中毒法测量微堆堆芯热中子绝对通量密度。
This paper introduces a design of digital neutron flux monitoring system for 10mw high temperature gas cooled reactor and its performances.
介绍了10MW高温气冷实验堆的数字化物理启动中子注量率监测系统的设计和功能。
The measured value of integrated thermal neutron flux was compared with the calculated value.
测得的热中子积分通量值与计算值作了比较。
Theoretical estimate of neutron fluxirradiation includes the dose equivalent of fast flux, thermal flux and fast flux at the skin and their total amount.
中子束辐照的理论估算包括快中子、热中子和快中子表皮剂量当量的确定及总剂量的范围。
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.
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。
The associated particle method was used to determine the absolute neutron flux and compared with the recoil proton telescope. The agreement between both methods appeared to be within 1—2%.
中子通量用伴随粒子法测定，并与反冲质子望远镜相比较，两种方法在1—2%的误差范围内一致。
Horizontal radiation ducts in research reactors are used to reduce the high energy neutron flux from near the core.
研究堆中水平辐照孔道用以从堆芯附近引出高能中子流。
Also, the neutron flux monitor, energy calibration and Uranium target parameters are discussed in detail.
对中子注量监测、能量刻度和铀靶参数的有关问题也进行了分析。
Also, the neutron flux monitor, energy calibration and Uranium target parameters are discussed in detail.
对中子注量监测、能量刻度和铀靶参数的有关问题也进行了分析。
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