| 单词 | neutron flux |
| 释义 | 例句释义: 中子通量,中子流,中子通率,中子通量密度,高能量中子通量 1. Threshold detector calibration by utilization of a natural uranium converter for fast neutron flux measurements. 通过天然铀换能器在快中子通量测量中的应用校正阈值探测器…[中国核科技信息与经济研究院]。 210.82.31.83 2. Neutron flux characterization of a peripheral target position in the high flux isotope reactor. 高通量同位素反应堆中靶子位置周边中子通量特征…[中国核科技信息与经济研究院]。 210.82.31.83 3. The corrections for neutron flux attenuation , multiple scattering and finite angle resolution are performed using Monte - Carlo method . 用蒙特卡罗方法进行中子通量衰减，多次散射和有限角分辨的修正。 www.bing.com 4. Thermal neutron flux and heating in the upper thermal shield of a graphite reactor. 石墨反应堆上部热屏蔽层的热中子通量和加热…[中国核科技信息与经济研究院]。 210.82.31.83 5. Influence of focusing curvature radius on neutron flux was investigated. 考察聚焦曲率半径对中子注量率的影响； paper.pet2008.cn 6. 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。 blog.emuch.net 7. Monitoring fast neutron flux inside spent reactor fuel by CR-39 detector. 用CR-39探测器进行反应堆乏燃料内快中子通量的监测…[中国核科技信息与经济研究院]。 210.82.31.83 8. Comparison shows neutron flux decreases to 24. 3% at thermal channel exit and 6. 7% at guide exit. 比较发现，经过水平孔道后中子注量率下降为源处的24.3%、导管末端下降为6. paper.pet2008.cn 9. 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 www.ilib.cn 10. Simulation Study of Double Values Dynamic Matrix Control of the Nuclear Reactor Neutron Flux Density 核反应堆中子通量密度的双值动态矩阵控制仿真研究 ilib.cn 1. Measurement and adjustment of neutron flux spectrum on shielding-experimental reactor of Tsinghua University 清华屏蔽实验反应堆中子注量率能谱的调节和测量 ilib.cn 2. 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 www.ilib.cn 3. Study on Generalized Predictive Control for the Neutron Flux Density of the Nuclear Reactor 核反应堆中子通量密度的广义预测控制方法研究 www.ilib.cn 4. Neutron flux density measurement system in commercial mini-neutron-source-reactor 商用微型研究堆中子注量率密度检测 ilib.cn 5. Calculation of absolute thermal neutron flux density in the core of miniature neutron source reactor 微型中子源核反应堆绝对中子通量密度计算 ilib.cn 6. Fast Neutron Flux Calculation of Welding Line in Pressure Vessel of High Flux Engineering Test Reactor 高通量工程试验堆压力容器焊缝快中子注量计算 www.ilib.cn 7. 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 service.ilib.cn 8. 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 www.ilib.cn 9. Measurement of absolute neutron flux by Eu activation transition method Eu活化过渡法测量绝对热中子注量率 www.ilib.cn 10. Nonlinear Control of Neutron Flux Density of the Nuclear Reactor 核反应堆中子通量密度的一种非线性控制方法 service.ilib.cn 1. 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 ilib.cn 2. A parametrized approach for resolving the neutron flux spectrum 反应堆中子注量率谱的谱参数法解 www.ilib.cn 3. 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 www.ilib.cn 4. Nuclear reactor in core neutron flux instrumentation 核反应堆中心中子通量测试设备 www.eavic.com.cn 5. diffusion coefficient for neutron flux density 中子通量密度扩散系数 www.bing.com 6. Development of Neutron Flux Data Acquisition System with Multiple Space-Time Channels 多时空通道中子数据采集系统研制 service.ilib.cn 7. The measurement of neutron flux from static accelerator 加速器中子源的中子注量测量方法 ilib.cn 8. Measurements and Corrections Methods for Neutron Flux in UHZr Reactor Center Porthole 铀氢锆堆中央孔道中子注量测量及校正 ilib.cn 9. Neutron flux measurement in neutron beam equipment by SSNTD 固体径迹探测器测量束流装置内的中子通量密度 service.ilib.cn 10. 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 www.ilib.cn 1. Nuclear Track Method to Measure Neutron Flux 固体核径迹法测量中子注量研究 ilib.cn 2. In core neutron flux measurement 堆芯中子通量密度测量 www.chinanuclear.cn 3. 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 ilib.cn |
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