Dear Alireza;

Of course you can obtain the certain dose values in MCNPX code. If you are interest with energy deposition in a cell or point, you have to use F6 tally mesh otherwise, if you interest with average flux in a cell or point then you have to use F4 tally mash. Of course, each of them have a definition style in input file. For further information, you can contact with me directly.. Also, i can offer you to take a brief look to User Manual of MCNPX. There you can find everything..

Good Luck..

Dear Hüseyin;

Thanks for your attention and your offer, however i have used the F6 tally, but this tally only shows the energy deposition(mev/g) in each cell whereas i need the PDD(percentage depth dose) value which is a percentage. Do you imply i should use this tally in order to assess PDD? If so, how should i do that? Is there any formula that i should place the F6 tally value and obtain the PDD value?

Dear Ali Reza;

Maybe this article can help you

https://www.ncbi.nlm.nih.gov/pmc/articles/PMC3607340/

PDD is obtained by dividing the calculated or measured dose to the dose at certain point(it is usully the maximum value). thus if you want to compare the calculated and measured  PDDs you should choise the point as same as measurement. I also recommend the *f8 tally instead of f6 and f4 tallies.

You can also read the attached useful paper.

Dear Farhad;

Thanks a lot for the attached paper. It was really helpful.