There appeared to be no gross distortions of the neutron spectrum expect at energies below 2 MeV. 除了2兆电子伏以下的能量外,中子谱似乎不存在显著的畸变。
This flexibility can only be assured with the deployment of the fast neutron spectrum reactor technology, and fuel reprocessing. 这种灵活性只能保证与快中子谱反应堆技术的部署和燃料后处理。
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
Neutron Spectrum Measurement with Activation Method in Sample Place of On-line Neutron Activation Analysis System 活化法测量中子活化在线分析系统样品处的中子能谱
Unfolding Whole Energy Range Neutron Spectrum from Activation Data by Nonlinear Programming Method 活化技术测中子全谱的非线性规划法
Studies on Unfolding of Fast Neutron Spectrum Measured with SSNTD SSNTD快中子能谱测量解谱技术研究
The incident neutron spectrum at the experimental condition has been simulated with the code MCNP, and the scattering neutron influence has been calculated with the spectrum. 并用MCNP程序模拟了在高压倍加器的实验条件下的散射中子能谱,进而计算了低能散射中子引起的修正量。
Thermal neutron spectrum of zirconium hydride moderator 氢化锆慢化介质中的热中子能谱
Neutron Spectrum Computed with Monte Carlo Method of Nuclear Warhead 核弹头泄露中子能谱的蒙特卡罗计算
There are two steps for the solution of a neutron spectrum: first, the spectrum function based on Westcott's parameters is used, and these parameters are determined by a non-linear least-squares fit of the reaction rates both for observation and calculation; 中子解谱分为两步:首先利用以韦斯科特(Westcott)参数为基础的谱函数,通过对反应率的观测值和计算值进行非线性最小二乘法拟合,求得待定参数;
Calculation of neutron shielding with the emitted neutron spectrum of heavy ion reaction 根据重离子反应出射中子能谱计算中子屏蔽
A preliminary study of an arbitrary neutron spectrum equivalence by multisource synthesis 多元合成法研究任意中子源能谱等效的尝试对氯苯甲醛的合成
The study of the influence of neutron scattering by the surrounding medium and fragment detector on fission neutron spectrum measurement with time-of-flight ( TOP) method has been carried out. 介绍了用飞行时间方法测量裂变中子谱时中子在裂变碎片探测器上和周围材料上散射的影响。
Conclusion If once neutron spectrum and fluence incident on human body in a accident are determined, using F_D ( E) the receiving absorbed dose of entire body of the patient can conveniently be calculated. 结论在事故时入射到人体上的中子谱及中子注量一旦被确定,使用FD(E)就能方便地计算出受照射者的全身中子吸收剂量。
The moderation of neutron in light water and the impact of neutron reflector on neutron spectrum are investigated with the Monte Carlo method. 用MonteCarlo的方法研究了中子在水中的慢化和反射层对中子能谱的影响。
The neutron spectrum of D-D reaction in ultraintense laser-plasma interaction is calculated. From the result of above tests, optimal reaction solution was obtained. 对超强激光与等离子体相互作用过程中发生的氘-氘反应的中子能谱进行了计算。
A method of an arbitrary neutron spectrum equivalence for damage in semiconductor by multisource synthesis was described. 描述了一种多元合成研究任意中子源对半导体辐照损伤能谱等效的方法。
The evaporation model theory for the fission prompt neutron spectrum of heavy nuclei 重核裂变瞬发中子能谱的蒸发模型理论
Application of solid state track detectors in measurement of neutron spectrum 固体径迹探测器在中子能谱测量中的应用
It was found that the neutron scattering influence on the fission neutron spectrum is rather essential and can noticeably change the shape of the fission neutron spectra. 结果表明,中子散射对裂变中子谱的影响是相当重要的,它能明显地改变裂变中子谱的形状。
Solution of neutron spectrum by least-square method 用最小二乘法求解中子谱
Thermal Neutron Spectrum in Thermal Column of Pulse Reactor Measured Techniques With Time of Flight Method 飞行时间法测量脉冲堆热柱孔道热中子能谱
Realization for solving the neutron spectrum on Microcomputer 微机上求解中子谱的实现
ρ R in high compression state can be given by measuring the secondary neutron spectrum of pure deuterium fuel implosion. 通过测量充纯氘燃料靶丸的次级中子能谱,可以给山高压缩状态卜的ρR。
Unfolding neutron spectrum with response functions and pulse height distributions is a key technique in the filed of neutron detection, and it is of great value to both scientific research and practical application. 基于探测器响应函数和脉冲幅度谱反演中子能谱作为中子探测的一项关键技术,具有极其重要的科学研究和实际应用价值。
It is necessary to know the accurate neutron spectrum in many fields, such as nuclear physics research, reactor techniques, accelerator operation, space exploration, radiological protection and so on. 在核物理研究、反应堆控制、加速器技术及空间探测、核辐射防护等领域,都需要精确了解辐射场内中子能谱分布。
To get the ion temperature Ti and the fuel density ρ R under such low neutron yield, we need to establish a large area neutron detector array to measure the time-of-flight neutron spectrum. 为了在这样低的中子产额条件下获得离子温度Ti和ρR,需要建立一套大面积中子探测器阵列测量中子的飞行时间谱。
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。