neutron flux density

Logarithmic power measuring assembly based on the neutron flux density

根据中子通量密度的对数功率测量装置

A predictive control method of the neutron flux density for a nuclear reactor

核电站反应堆中子通量密度的一种预测控制方法

Measurement of Absolute Neutron Flux Density by Peak Area Ratio Method

峰面积比法测量绝对热中子注量率

Development of data acquisition software for neutron flux density temporal and spatial distribution

中子注量率密度时空分布数据采集软件开发

The new method for thermal neutron flux density measurement by γ spectrometer is described .

介绍了利用γ谱仪测量绝对中子注量率的方法。

Simulation Research of Reactor Neutron Flux Density

反应堆中子通量密度仿真研究

Project on neutron flux density data acquisition system with multiple space-time channels based on a microcomputer

多时空通道中子注量率密度数据采集系统方案设计

Measurement of absolute thermal neutron flux density in the core of miniature neutron source reactor

中毒法测量微堆堆芯热中子绝对通量密度

Neutron Flux Density of Horizental Direction Distribution for Sealed Small-Sized Neutron Generator

小型密封式中子发生器中子通量密度的水平方向分布

This paper introduces 32-bit data acquisition software of neutron flux density temporal and spatial distribution on Windows 98 Platform .

介绍基于Windows98平台的中子注量率密度时空分布32位数据采集软件。

Neutron flux density scanning assembly

中子通量密度扫描装置

Time-resolved Neutron Flux Density Measurement on HT-7 Superconducting Tokamak

HT-7超导托卡马克上时间分辨中子注量率测量

Neutron flux density indicator

中子通量密度指示器

Calculation of neutron flux density and the activity measurement of ￣( 56 ) mn by 4 πβ - γ coincidence absorption method

用4πβ－γ符合吸收法测量~（56）Mn的活度并计算中子注量率

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。

Meanwhile , the thermal neutron flux density at certain point is measured and then the thermal neutron flux density per unite power is given .

同时，测量了对应功率下反应堆内辐照座的热中子通量密度，得到单位功率的热中子通量密度，即额定中子通量密度下的运行功率。

Monte-Carlo calculation of K_ ( eff ) and neutron flux density in fast neutron critical assemblies with multi-group section data

用多群蒙特卡罗方法计算快中子核临界K（eff）和通量密度

The neutron flux density ratio , Au-Cd ratio , Mn-Cd ratio at various positions in special neutron beam equipment are measured by gold foil method .

利用金箔活化法测量了特殊束流装置中心轴线上不同位置处的热中子通量密度比、金镉比、锰镉比以及出口处γ/n的剂量比。

The thermal neutron flux density is measured with Soild State Nuclear Track Detector ( SSNTD ), and the γ radiation dose rate is detected with Thermoluminescence Dosimeter ( TLD ) .

中子通量密度采用固体核径迹探测器测量，γ辐射剂量率用热释光探测器测定。

Based on the " measured " neutron flux density distribution reconstructed by using harmonics synthesis method ( HSM ) from the readings of in-core neutron detectors and some necessary restrictions of core parameters , a procedure is proposed to calibrate the core parameters after burn-up .

文中提出：在用芯内中子探测器读数重构出测量的全堆热群中子通量密度分布的基础上，约束堆芯截面参数，并采用节块格林函数法对其进行校准的一套完整方法。

A sort of non-parameter model is constructed with the unit step response of the nuclear reactor neutron kinetics system . Furthermore , a sort of constant neutron flux density control law is presented using a predictive control algorithm .

利用核电站反应堆中子动力学系统的单位阶跃响应数据，获得了该系统的非参数模型，且提出了一种中子注量率恒值问题的预测控制方法。