A multigroup Monte Carlo Code MCMG is developed based on the continuous-energy Monte Carlo Code MCNP.
基于连续能量蒙特卡罗程序MCNP开发了多群蒙特卡罗程序MCMG。
MCNP is an advanced general purpose and extra large coupled neutron photon Monte Carlo transport code system.
MCNP是一个超大型、先进的多功能蒙特卡罗中子-光子耦合输运程序，在世界范围内得到了广泛的应用。
The original spectrum from the soil is simulated by MCNP and the experiment of influence to natural gamma-ray is done.
采用MCNP模拟软件和水分对天然伽玛射线的影响实验，对不同水分土壤中铀系和钍系天然伽玛的原始谱进行了模拟运算。
The Monte Carlo calculating software packet was developed for wall epithermal neutron time-spectrometry logging on the basis of MCNP.
在此基础上，再研究井壁超热中子时间谱测井仪或井壁超热中子测井仪的工程参数。
Based on the Monte Carlo MCNP code, the changes of radiation dose at the shield water tank surface during the process of lost water is studied.
基于蒙特卡罗方法的MCNP程序，研究了反应堆屏蔽水箱失水过程中的水箱表面辐射剂量的变化情况。
MCNP is an advanced general purpose and extra large coupled neutron photon Monte Carlo transport code system. It has very wide range of application.
MCNP是一个超大型、先进的多功能蒙特卡罗中子-光子耦合输运程序，在世界范围内得到了广泛的应用。
MCNP/4B code was used to calculate the activation reaction rates on the experimental device. The calculated results are compared with the experimental ones.
用MCNP/4B程序计算了实验装置上的活化反应率，并与实验结果进行比较。
To calculate burnup for the cores with fast neutron spectrum, we have written the linking codes to process the input and output of MCNP code and ORIGEN2 code.
采用通过编写连接MCNP程序和ORIGEN2程序的接口处理程序的方法进行快中子系统的燃耗计算。
The paper focuses on the introduction of modelling of the core and reflector. The core description is simplified by using repetition structure function of MCNP.
着重介绍堆芯和反射层的建模，利用MCNP程序的重复结构功能简化对堆芯的描述。
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。
Based on MCNP, authors developed the software package of the Monte Carlo method to simulate the neutron flux distributions with the space, energy and time for neutron logging.
作者在MCNP的基础上，开发了中子测井，中子通量随能量、时间分布蒙特卡罗(MC)模拟软件包。
On the basis of the introduced experimental information, the process of calculating the effective multiplication factor of MOX fuel experimental reactors using MCNP is introduced.
简单说明计算所用的实验资料，在此基础上，介绍了采用MCNP计算MOX燃料实验堆有效增殖系数的过程。
MCAM is a software used for MCNP automatic modeling and visualization. This article presents the principle, approach and the implementation of MCNP neutronics model visualization.
是MCNP自动建模与可视化软件，重点介绍MCAM中MCNP中子学模型可视化的原理、技术及实现。
With MCNP/4B code, the influence of cut-off energy, flux tallies, nuclear databases and perturbation on the reaction rates calculation with neutron-activation method are analysed.
用MCNP／4B程序，对核活化法反应计算中的截断能量、通量计数方式、数据库、阈探测器之间的扰动等因素的影响作了分析。
Analysis on the relationship between the text description of MCNP neutronics model and the CSG shows that the conversion from CSG to CAD model is the key issue of the visualization.
通过分析mcnp中子学模型文本描述和构造立体几何表示法的关系，指出从构造立体几何表示法到CAD模型的转换是MCNP中子学模型可视化的关键所在。
Aiming at these problems, this paper analyses the effect trend and degree of several different factors to the problems by using MCNP simulation. This work provides references for system designing.
针对这些，进行MCNP仿真实验，分析各种因素对不同测量单元散射线干扰及探测到射线强度的影响趋势和影响程度，为实际系统的设计提供参考。
Aiming at these problems, this paper analyses the effect trend and degree of several different factors to the problems by using MCNP simulation. This work provides references for system designing.
针对这些，进行MCNP仿真实验，分析各种因素对不同测量单元散射线干扰及探测到射线强度的影响趋势和影响程度，为实际系统的设计提供参考。
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