MCNP/4B在MOX燃料临界计算中的应用

说明MOX燃料元件在核燃料循环过程中的意义及采用的计算方法．介绍了计算所用的实验资料，在此基础上，采用蒙特卡罗计算程序MCNP／4B计算了MOX燃料实验堆的有效增殖系数，在计算结果的基础上评价了MCNP／4B在MOX燃料实验堆计算中的有效性．同时在计算过程中引入一种建立输入卡的技巧．最后，讨论数据库对计算结果的影响，并分析了计算结果和实验值之间的误差来源．

Application of MCNP/4B to critical calculation of MOX fuels

The significance of MOX fuels in the cycle of nuclear fuels and calculation method were explained. On the basis of experimental information, calculations of the effective multiplication factor of MOX fuels experimental reactors were made by use of Monte Carlo MCNP/4B program. The effectiveness of MCNP/4B in the calculations of MOX fuels experimental reactors was assessed based on the computational results. A technique called input cards was introduced in the computation. At last, the influence of database on calculation results and the sources of errors between results and experimental values were discussed.