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。
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。
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。
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。
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。
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。
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。
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。
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。
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