Hello OpenMC users,
I want to calculate the current (number of neutrons) at the surface of a cube. If I understand correctly, for the current, I can use either a cell filter or a surface filter. If I want to use a surface filter, I can define a plane, but I don’t know how to set limits in the y and z directions to get a surface filter with specific dimensions to use for ‘current’ tally. Many thanks for your help!