Recent content by LeeGru

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

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...

Thank you very much.I need to calculate the ratio between the total neutron current and the total neutron flux.How could I obtain this value in MCNP

I need to calculate the ratio between the total neutron current and the total neutron flux.How could obtain this value?

Guys,I need to calculate the flux and current of neutron by MCNP.So what's the difference between them ,and How to calculate them? Any ideas?