MCNP source code MCNP源程序
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。
应用推荐