COMPARISON OF THE MONTE CARLO CODES MCNP AND MONACO IN SHIELDING CALCULATIONS FOR TRANSPORT/STORAGE CASKS

The Monte Carlo code for shielding calculations of transport/storage casks, such as the MCNP and MONACO codes which are included in the SCALE code system, are compared in this paper. The comparison includes the calculation with both a simplified and a more detailed cask model to check the difference between the two codes concerning the capability of input data and the trend of the obtained results. The results show that both codes are very useful and obtain reasonable results within the reasonable CPU time. The MONACO code is better to get reasonable results with shorter CPU time than MCNP code when the input data is used in a simplified case. When the input data becomes more complicated the MCNP code is better. The obtained neutron/gamma dose rates are reasonably similar to each other.