中子注量率

300堆池内结构部件中子注量率测量实验研究

Experimental study on the measurement of neutron fluence rate of SPRR-300 Reactor in-pool components

50MeV/u~（12）C离子实验靶区中子注量率的测量

Measurement of neutron fluence rate in 50MeV / u ~ ( 12 ) C-ion experimental target area

用4πβ－γ符合吸收法测量~（56）Mn的活度并计算中子注量率

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

HT-7超导托卡马克上时间分辨中子注量率测量

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

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

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

SPRR-300反应堆辐照孔道中子注量率的MCNP程序计算

Calculation of Neutron Flux in SPRR-300 Reactor Irradiation Channel with MCNP Code

SPRR-300反应堆大热柱内中子注量率及能谱分布

Neutron Fluence Rate and Energy Spectrum in SPRR-300 Reactor Thermal Column

SPRR-300反应堆混凝土屏蔽层内中子注量率分布研究

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

用活化法测量SPRR-300堆芯相对中子注量率分布

To measure relative neutron-flux distribution in the core of SPRR-300 by use of activating method

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。

This paper introduces a design of digital neutron flux monitoring system for 10MW high temperature gas cooled reactor and its performances .

利用MCNP程序的重复几何结构功能，对SPRR-300的堆芯几何结构进行了简化处理，建立了该堆辐照孔道中子注量率分布计算的数学模型。

The issue predigests geometric structure of SPRR-300 reactor core with repeated structure geometry feature of MCNP code and sets up the irradiation channel mathematical model to calculate the neutron flux .

用MCNP／4B计算了脉冲堆稳态堆芯第一循环插棒前后探测器位置的中子注量率，得到了探测器位置的空间因子。

With MCNP / 4B code , Neutron flux at detector position in Pulsed Reactor has been calculated when the rods were at the top and the bottom position . The spatial factors at the detector have been calculated .

峰面积比法测量绝对热中子注量率

Measurement of Absolute Neutron Flux Density by Peak Area Ratio Method

应用标准铀玻璃进行中子注量率测定

Determination of neutron fluence rate using fission track glass standard

靶件内中子注量率分布计算方法研究

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

核电站反应堆中子注量率的预测控制仿真研究

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

一套新型的中子注量率绝对测量系统

A New Type of Neutron Flux Absolute Measurement System

固体径迹探测器测量绝对中子注量率的一种简便法

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

清华屏蔽实验反应堆中子注量率能谱的调节和测量

Measurement and adjustment of neutron flux spectrum on shielding-experimental reactor of Tsinghua University

热中子注量率测量方法研究

Study on measuring method of thermal neutron fluence rate

反应堆中子注量率谱的谱参数法解

A parametrized approach for resolving the neutron flux spectrum

中子注量率密度时空分布数据采集软件开发

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

反应堆中子注量率和周期测量仪

The reactor neutron flux and period measure meter

用固体核径迹探测器测量反应堆周围的快、热中子注量率分布

Measurement of distribution of fast and thermal neutron fluence rate around reactor with SSNTD

白云母迹径探测器测量宽范围的绝对热中子注量率

Measurement of absolute thermal neutron fluence rate in wide range with muscovite track detector

反应堆内中子注量率新型探测器的理论研究

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

介绍了利用γ谱仪测量绝对中子注量率的方法。

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

多时空通道中子注量率密度数据采集系统方案设计

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

用伴随粒子法测量加速器聚变中子注量率

The Measurement of the Fluence Rate of Accelerator Fusion Neutrons by Using the Associated Particle Method

300~-1靶片内热中子注量率分布测量实验研究

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