摘要：MCNPX is a general purpose Monte Carlo radiation transport code designed to track many particle types over broad ranges of energies and it has the potential to deal with Accelerator Driven System(ADS)*** neutronics design and analysis of ADS using MCNPX code is significantly complex mainly on constructing the three dimensional geometry model,especially when there is an additional spallation target coupled with the subcritical reactor constructed by abundant nested repeated structures in several *** modeling process has long been recognized as a time consuming,tedious and error-prone task,which is hard to master for novice ***,it is imperative to build a code system that can translate CAD models of ADS to the native language of MCNPX *** this context of demand,a code system named CAD-PSMC(FreeCAD based parsing script for MCNPX code)has been developed to solve the CiADS modeling conversion problems.