Hi everyone, I am new to Openmc and I am doing a fixed source calculation for reactor shielding. I defined a cylindrical mesh in my RPV region (i.e. from its starting to its ending). Now the flux score in the tally is in n.cm/s as far as I know( read that in the documentation). Now to calculate the flux in usual units n/cm^2.s I need to multiply this flux in the tally by mesh volume but how to calcualte this mesh volume bcz in my case I have defined my mesh like this
Radial and axial mesh edges
r_grid = np.linspace(100, 120, num=11) # 10 radial bins
z_grid = np.linspace(-50, 50, num=11) # 10 axial bins
Collapse phi into a single bin
phi_grid = [0.0, 2*np.pi] # Just one full circle
Construct the cylindrical mesh
mesh = openmc.CylindricalMesh(r_grid=r_grid, z_grid=z_grid, phi_grid=phi_grid)
where I have not done the meshing in phi. now the mess cell volume i can think of is 2pirdrdz now dr and dz in my case would be lets say 1cm, but r will change as I go inside the RPV so is it the right way to do it or is there some other way to do this