It is showed that compensated neutron logging can be realized by using neutron generator instead of isotopic neutron source. 结果表明,可以用中子发生器代替同位素中子源实现补偿中子测井。
Neutron Spectrum Measurement From Am-Be Neutron Source in Radiation Shield Cavity 阈探测器法测量Am-Be中子源屏蔽辐照腔内的中子能谱
Sealed neutron source and gamma source used in nuclear logging have strong radioactivity which is harmful to operators. 核测井使用的密封中子源和伽马源具有较强的放射性,对操作人员有一定的辐射损伤。
Research on Beam-shaping-assembly of D-T Reaction Neutron Source and Beam Characteristic D-T反应中子源准直屏蔽体及中子束特性研究
It reports a study on the design optimization of a two-axis diffractometer installed at a steady neutron source, dedicated to stress measurements. 主要是针对稳态堆上专门做应力测量的两轴谱仪优化设计的研究。
Calculations of Dose and Ambient Dose Equivalent in Radiation Field for Am-Be Neutron Source Am-Be中子源辐射场周围剂量当量与吸收剂量的计算
The degree of neutron yield stability was an important parameter for pulse neutron source. 中子产额的稳定度是脉冲中子源的一项重要指标。
Specification of nuclear fuel rods for miniature neutron source reactor GB/T13368-1992微型中子源反应堆核燃料棒技术条件
The Effect of Low Energy Neutrons From Monoenergetic Neutron Source on Activation Cross Section Measurements 单能中子源中低能成份对活化截面测量的影响活塞式变截面流量计
Research on γ Measurement System of Neutron Source Strength Standard with a Manganese Sulphate Bath Method 锰浴法中子源强度基准的γ测量系统研究
The subcritical reactor physics properties for ADS is studied and analyzed under different external neutron source. 通过对多种外中子源输入的模拟计算,研究分析了ADS系统中次临界堆的物理特性。
The neutron spectra from the gas discharge facility and D-D neutron source are compared. 并与加速器D&D中子源的中子能谱进行了比较。
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。
Various calibration methods are discussed in detail, with calibration curves and coefficients obtained for three distances based on the method for stopping the radiation after the detector is saturated using an accelerator type neutron source. 详细讨论了探测器的标定方法,用饱和照射后截止的方法,在加速器中子源上给出了3个探测距离下的标定曲线和标定系数。
Research on Neutron Source Multiplication Method in Nuclear Critical Safety 核临界安全中的源倍增法研究
The neutron fluctuation behavior in near critical nuclear system with a weak neutron source is treated with Markov process. 在近临界核系统中,弱源中子的涨落行为是一个典型的Markov分支过程。
The computer safety monitoring system was established for miniature neutron source reactor ( MNSR) of Shenzhen University. 在深圳大学微堆上建立了计算机安全监督系统。
Calculations of intensity and spectra of white light neutron source produced by 70 MeV proton accelerator 70MeV质子加速器产生的白光中子源强度和能谱的计算
A thermal neutron beam equipment is installed in the miniature neutron source reactor ( MNSR) zero power facility. 在微型反应堆零功率装置上搭建了硼中子俘获治疗拟采用的热中子束流装置。
The relation between statistical errors of measured data and the spectrum of white light neutron source is specially discussed. 此外还特意讨论了实验测量截面值的统计误差与白光源中子谱的相关性。
The neutron source intensity and relevant physical parameters for driving the reactor with the different subcritical states are given. 给出了驱动不同次临界度包层所需的中子源强度及其相应的物理参数。
The paper gives experiment theory and experiment method of neutron source multiplication method for site measurement technology in the nuclear critical safety. 给出了核临界安全中监督现场的测量技术&源倍增法的实验理论和实验方法。
A time interval formula for neutrons emitted by an isotope neutron source and reacted by a medium is derived. 用数理统计方法推导了同位素中子源发射的中子经介质作用后相邻中子时间间隔的表示式。
The theoretic programs and Monte Carlo codes are a useful approach for solving the physics of spallation neutron source. 相关的理论计算程序和蒙特卡罗方法是研究该系统的散裂靶物理的一个重要手段。
Neutron source multiplication method research in reactor physics experiment 反应堆物理实验中的源倍增法研究
The Spallation Neutron Source is a huge scientific research devices and a multi-disciplinary services platform. 散裂中子源是一种大型科研实验装置,是服务多学科的大平台。