Which Tally type should I use in MCNP6?

[khary23]

I have a problem where I want to model the dose in Gy of a gamma source on a surface as a function of distance. In the papers I have read several different tallys have been used which leaves me a little confused as to the appropriate tally. In the papers the *F4Mesh, F4, F6, and *F8 tallys were used.

 

[jedishrfu]

Can you tryout each one and decide from that?

 

[PSRB191921]

Hi,
the first question you need to answer is "What I want calculated ?" :
- dose,
- kerma,
- dose equivalent,
- equivalent dose