- #1
froztiz
- 6
- 0
Hi everybody,
I am trying to score fission spectrum in MCNP for a kcode calculation. I would like to check at which energy neutrons produced by fission are generated. I have no idea how to perform since tallies are usually volume or material dependent and I just want to build a spectrum containing only the neutrons created by fission.
Any idea on how to proceed?
I am trying to score fission spectrum in MCNP for a kcode calculation. I would like to check at which energy neutrons produced by fission are generated. I have no idea how to perform since tallies are usually volume or material dependent and I just want to build a spectrum containing only the neutrons created by fission.
Any idea on how to proceed?