neutron flux

1. Neutron flux measurement and analysis in the HT-7 deuterium plasma
   HT-7上氘等离子体放电时中子注量的测量与分析
2. 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。
3. 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
4. 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
5. Neutron flux density indicator
   中子通量密度指示器
6. In order to reduce the loss of neutron flux, neutron reflectometer design usually use the neutron guide to transport neutron beam, forepart of the neutron reflectometer is the shutter.
   为减少中子注量的损失，中子反射谱仪的设计通常需要采用中子导管来传输，最前端为中子束流闸门。
7. Counter tube fast neutron flux meter
   计数管式快中子通量计
8. Neutron flux density scanning assembly
   中子通量密度扫描装置
9. Source range neutron flux channel
   源区段中子通量通道
10. 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。
11. Neutronics calculations of neutron flux monitor for ITER
    ITER中子通量监测器的中子学计算
12. Fast-response miniature neutron flux monitor
    快速响应小型中子通量监测器
13. 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。
14. The cadmium ratio RCA and thermal neutron flux are usually measured in a re-'actor.
    镉比R（Cd）和热中子通量是堆内常测的参数。
15. 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。
16. 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。
17. The error analysis of finite-difference method in computing critical size and neutron flux is given. The exact solution in non critical case has been extrapolated from the exact solution in critical case.
    给出了有限差分方法计算临界尺寸和中子通量的误差分析，将临界情况下的精确解推广到了非临界情况。
18. 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。
19. 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。
20. In the zero-power experiment facility which is the 1:1 model of the core, the power distribution, non-uniform factor of the neutron flux and the absolute power of the pulsed reactor are measured by the automatic measurement system for neutron flux.
    本文简要介绍了在脉冲堆零功率实验装置上，利用中子通量自动测量装置进行的功率分布、中子通量不均匀系数和绝对功率的测量工作。
21. 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。
22. 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。
23. The origin of natural neutron flux on the air-ground interface has been introduce in this paper.
    介绍了地空界面天然中子流的来源和轻便型天然中子流测量仪器。论述了地空界面天然中子辐射场的扰动。
24. 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。
25. The transmission probability method is developed for solving neutron flux distribution in two-dimensional light water fuel assembly.
    本文讨论了用穿透几率法计算二维轻水堆燃料组件中子通量的分布，提出了一种简易的计算模型。
26. 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。
27. The high specific activity isotopes: 192 Ir and 60 Co in the high neutron flux reactor are calculated with the method of reactor physics.
    利用反应堆物理的方法，对使用高通量堆辐照生产高比度同位素192Ir和60Co的方案进行了计算。
28. Simulation Research of Reactor Neutron Flux Density
    反应堆中子通量密度仿真研究
29. 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。
30. The neutron flux in moderator cell, the neutron temperature and the neutron spectrum are analyzed for the optimal configuration, and these could conclude that analysis method and calculation results are correct and reasonable.
    在此基础上，对冷包内冷中子注量率、中子温度和中子能谱等也进行了分析，证明了计算和分析方法是正确的，优化方案的中子性能是合理的。

noun

1. the rate of flow of neutrons