中子通量
- 网络Neutron flux;neutron fluence
-
多群伴随中子通量积分方程的一种MonteCarlo新解法
A new Monte Carlo method for multigroup adjoint intergral equation of neutron flux
-
镉比R(Cd)和热中子通量是堆内常测的参数。
The cadmium ratio RCA and thermal neutron flux are usually measured in a re - ' actor .
-
HT-7超导托卡马克装置上中子通量分布的实验研究
Experimental study of neutron flux distribution on HT-7 superconducting tokamak
-
ITER中子通量监测器原型的研制
Development of a prototype neutron flux monitor for ITER
-
ITER中子通量监测器的中子学计算
Neutronics calculations of neutron flux monitor for ITER
-
对反应堆堆芯中子通量的计算首先介绍了传统的方法,包含Hermite插值、Gear方法、常源瞬跳等。
For the calculation of the reactor core neutron flux , the traditional methods is introduced first , including Hermite interpolation , Gear , Prompt jump approximate and so on .
-
当高能粒子进入慢化器后,会在慢化器中发生散裂反应与(n,2n)核反应,因此,反射体可以大大提高中子通量;
The reflector can increase the neutron flux obviously and the main processes of the neutron yield in reflector are spallation reaction induced by energetic hadrons and ( n , 2n ) reaction .
-
应用SSNTDs测量14MeV中子通量
Measurement of 14 MeV neutron fluences using SSNTDs
-
首先利用高能粒子输运程序NMTC/JAM计算了入射质子能量、靶的材料、形状、尺寸以及靶与慢化器耦合对中子通量的影响。
At first , the effect of the target on the neutron flux is discussed to determine the optimal proton energy , target material , shape and dimension by using the high-energy particle transport code NMTC / JAM .
-
该方法在时间方面,中子通量密度按时间二阶展开(QEM);在空间方面,采用Green函数节块法(NGFM)。
In the Temporal Quadratic Expansion Nodal Green 's Function Method ( TQE / NGFM ), the Quadratic Expansion Method ( QEM ) is used for the temporal solution with the Nodal Green 's Function Method ( NGFM ) employed for the spatial solution .
-
反应堆功率运行时,燃耗变化会引起堆外中子通量密度变化,造成RPN核功率测量系统测得的反应堆功率与实际功率出现偏差。
When the reactor is operating , the variation of the burn-up of the fuel will cause vari-ation of the neutron flux , which can make the core power measured by the RPN nuclear power system deviate from the actual power .
-
NPDMC程序可以计算各种类型的研究性反应堆和动力堆中的管道、束孔和缝隙的中子通量、能谱、剂量率和γ光子通量及剂量率等。
This program can calculate the following : flux , energy spectral , dose ration of neutron and flux , dose ration of photon in pipe , beam hole , gap for research reactor and nuclear power reactor shielding design and analysis .
-
六角形轻水堆组件中子通量密度分布的计算
Calculation for the Flux Distribution in Hexagonal fuel Assembly of LWR
-
用蒙特卡罗方法对快中子通量衰减和多次散射的修正计算
Calculations of fast neutron attenuation and multiple scattering corrections using Monte-Carlo method
-
反应堆中子通量分布测量及数据处理
The Measurement and Data Processing for Neutron Flux Distribution in Reactor Core
-
智能中子通量积分仪研制报告
The development report of an intelligent neutron fluence Integration Monitor
-
根据中子通量密度的对数功率测量装置
Logarithmic power measuring assembly based on the neutron flux density
-
测量了反应堆堆芯里的中子通量分布。
Neutron flux distributions in the reactor core are measured .
-
热堆内测量中子通量谱的可变容差法解
Solving measurement flux spectra in thermal neutron reactor with flexible tolerance method
-
固体径迹探测器测量束流装置内的中子通量密度
Neutron flux measurement in neutron beam equipment by SSNTD
-
零功率堆中子通量拟合的试验研究
The experimental research of neutron flux fitting method in a zero power reactor
-
界面流法计算反应堆六角形燃料组件中子通量密度分布
Calculation of Flux Distribution in Hexagonal LWR Fuel Assembly by Interface Current Method
-
低中子通量密度试验性反应堆
Dielectric ( flux ) density low intensity test reactor
-
核电站反应堆中子通量密度的一种预测控制方法
A predictive control method of the neutron flux density for a nuclear reactor
-
给出方法的数学模型,在节块内中子通量采用二次近似,表面泄漏采用常数近似。
The mathematical model of the method is presented .
-
在裂变径迹测定年代中准确测定中子通量
Accurate determination of neutron fluence in fission track dating
-
低造价的各向同性热中子通量基准■
A low cost isotropic thermal neutron flux field
-
零功率反应堆内中子通量相对分布实时测量
The on-line relative measurement of neutron flux distribution in the light water zero-power reactor
-
关于平板几何反应堆临界中子通量离散纵标法的收敛速度
Convergence rate of the discrete ordinate method for critical flux in a finite slab
-
反应堆快中子通量谱和载热剂比活性的计算
The Calculations of Reactor Fast Neutron Flux Spectrum and Specific Activity of Reactor Coolant