MCNP在次临界装置实验中的应用

  • 摘要: 介绍了应用MCNP3B程序对DF堆次临界装置的几个实验布置进行的物理参数计算, 并将计算结果与实验结果进行比较。通过对DF次临界装置的研究, 以求MCNP3B程序能为零功率实验提供指导性意见, 提高零功率实验的安全性。

     

    Abstract: MCNP code is a large multipurpose Monte Carlo code, can be used for radiation shielding calculation, application channel design, and some critical facility design. By the use of MCNP, some arrangement of DF sub critical facility is calculated, the results of calculation and experiment are comprised.

     

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