- #1
MadGander
- 21
- 1
- TL;DR Summary
- How does MNCP calculate an F6 Tally?
I'm wondering how exactly MCNP calculates an f6 tally? I'm trying to compare a theoretical result with an MCNP f6 tally (MeV/g). I have an initial energy spectrum and a thin layer of lead that attenuates the x-rays. Using the attenuation coefficient at each energy (bin width of 0.5 kev from 0-100 kev) and intensity at each energy, I produced an attenuated energy spectrum.
How do I compare this attenuated spectrum to an f6 tally? My thought process is to find the average energy within the spectrum and then divide by the mass of the f6 tally cell. However, this is a couple orders of magnitude off the MCNP ouput so I'm guessing it's wrong.
Another thing to note is that my average energy in the attenuated spectrum is higher than the average energy in an initial spectrum. The attenuator is a 0.08 cm thick lead sample, so there's no way the final average energy should be higher than the initial, right?
How do I compare this attenuated spectrum to an f6 tally? My thought process is to find the average energy within the spectrum and then divide by the mass of the f6 tally cell. However, this is a couple orders of magnitude off the MCNP ouput so I'm guessing it's wrong.
Another thing to note is that my average energy in the attenuated spectrum is higher than the average energy in an initial spectrum. The attenuator is a 0.08 cm thick lead sample, so there's no way the final average energy should be higher than the initial, right?
Last edited by a moderator: