Recent content by Caden

DEvens My experience with MCNP is lacking. Copied some of the MCNP output from a simple core that has fuel in a hexagonal formation shown below surrounded by water. I put F1 and F2 tallies on the top and bottom planes as well as the surrounding cylinder. The output from the the F1 tally...

I am running some depletion calculations and have noticed odd behavior when keff is much greater or lower than one in the number of absorption's taking place on the outside the reactor. MCNP seems to be deleting the neutrons after it has reached the number of fissions required for the power...