Neutron flux

The Measurement and Data Processing for Neutron Flux Distribution in Reactor Core

反应堆中子通量分布测量及数据处理

The experimental research of neutron flux fitting method in a zero power reactor

零功率堆中子通量拟合的试验研究

Research on methods for distribution of neutron flux in the experiment target

靶件内中子注量率分布计算方法研究

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 Network Communication Function for Digitalized Neutron Flux Monitoring Instrument

数字化核测量仪器的网络通讯功能设计

A New Type of Neutron Flux Absolute Measurement System

一套新型的中子注量率绝对测量系统

Simulation Study of the Neutron Flux Predictive Control for a Nuclear Reactor

核电站反应堆中子注量率的预测控制仿真研究

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

Theoretical Studies on the New System of Neutron Flux Measurement in the Nuclear Reactor

反应堆内中子注量率新型探测器的理论研究

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

Nodal of Green 's function method for adjoint neutron flux equations

格林函数节块法求解中子伴随通量方程

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。

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。

Fast neutron flux measurement uncertainty due to the variation of neutron spectra distribution

能谱变化对~（239）Pu裂变室测量快中子注量的影响

Experimental study for measuring distribution of thermal neutron flux rate in 300 ~ # - 1 target

300~-1靶片内热中子注量率分布测量实验研究

Simulation Research of Reactor Neutron Flux Density

反应堆中子通量密度仿真研究

Neutron Flux Response to Small Reactivity with Temperature Feedback

输入小阶跃反应性有温度反馈时中子增殖公式

A low cost isotropic thermal neutron flux field

低造价的各向同性热中子通量基准■

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

Monte Carlo simulation of neutron flux distribution with energy and time for water limestone formation

水灰岩地层中子随能量和时间分布的MonteCarlo模拟

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。

Nuclear Track Method to Measure Neutron Flux

固体核径迹法测量中子注量研究

A simple method for the determination of absolute neutron flux rate by SSNTD

固体径迹探测器测量绝对中子注量率的一种简便法

Study on neutron flux distribution in concrete shielding of the SPRR-300 reactor

SPRR-300反应堆混凝土屏蔽层内中子注量率分布研究

Digital Neutron Flux Monitoring System for Physical Startup of 10MW High Temperature Gas cooled Reactor

HTR-10高温气冷实验堆数字化物理启动中子注量率监测系统

Measurement of integral thermal neutron flux in a high flux reactor by the Co activation method

用钴活化法测定反应堆中热中子积分通量

Experimental study of neutron flux distribution on HT-7 superconducting tokamak

HT-7超导托卡马克装置上中子通量分布的实验研究

The reactor neutron flux and period measure meter

反应堆中子注量率和周期测量仪

The on-line relative measurement of neutron flux distribution in the light water zero-power reactor

零功率反应堆内中子通量相对分布实时测量