How to use mesh tally in MCNPX to calculate dose?

[LeeGru]

Hello,guys,
I wonder how to use mesh tally to calculate dose.I set a cylinder，and set the material of the cylinder.Then I want to divide a cylinder into smaller cylinders in a direction perpendicular to the z-axis.And I need to record the flux of each mesh,use dedf card to get dose.
I have tried to write a little bit, please help to see if it is correct and what needs to be added?
The radius of big cylinder is 7cm,length of it is 10cm,the radius of little cylinder is 7cm,too,the length of little cylinder is 1mm.
TMESH
CMESH1:n
CORA1 0.0 7 99r
CORB1 0 100i 10
CORC1 0 179r 360
ENDMD

 

[PSRB191921]

Hi,
after "CMESH1:n" you must put the keyword DOSE and the options (int iu and fact)
see 3.3.5.24.2 of the MCNP6 version 1.0 manual,

 

[LeeGru]

Hi,
after "CMESH1:n" you must put the keyword DOSE and the options (int iu and fact)
see 3.3.5.24.2 of the MCNP6 version 1.0 manual,

Thank you!However,I don't have MCNP6.I'm using MCNPX,and could you tell me more details?
Thank you very much!

 

[PSRB191921]

Hi
in MCNPX 2.5.0 manual (LA-CP-05-0369) see 5.6.22.2
For an another version of MCNPX try to search "TRACK-AVERAGED MESH TALLY" in the manual