parazit said:
Thanks a lot for reply. But, can you explain depletion calculation means? If you don't have any objection, you can explain by example. thxStephan_doc said:the MCNPX can be used for depletion calculations
MCNP5 and MCNPX are both computer codes used for simulating and analyzing the transport of particles through matter. They are both based on the Monte Carlo method, but have some key differences in their functionality and capabilities.
The choice between MCNP5 and MCNPX depends on the specific requirements of your project. MCNP5 is better suited for neutron and photon transport, while MCNPX has more advanced capabilities for electron and proton transport. Consider the type of particles and energies you are working with in your project to determine which code is more appropriate.
Both MCNP5 and MCNPX have a similar user interface, with options for input files, geometry definitions, and output data. However, MCNPX has a more user-friendly graphical user interface (GUI) compared to MCNP5, which may be preferred by those who are new to the codes.
Yes, it is possible to use both codes for the same project. In fact, some researchers use both codes to compare results and validate their simulations. However, it is important to note that the input parameters and settings may need to be adjusted to ensure consistency between the simulations.
MCNP5 and MCNPX are developed by different teams and have some differences in their coding, so there may be some compatibility issues when transferring input files between the two codes. It is recommended to double-check the input file and make any necessary adjustments before running simulations in a different code.