- #1
Andrev
- 17
- 0
Hi,
I'm working on a MCNP simulation where I have to use F6 tallies. According to the manual: "In the F6 and +F6 tallies, material density is available for the chosen cells, and normalization is MeV/gm/source-particle."
To which source-particles is this value normalized: the source-particles in the chosen cell or the source-particles of the whole simulation?
(Example: Let's say I have two cells (cell1 and cell2) in the simulation, both tallied. If I would like to get cell1's MeV/gm energy density with which amount of source-particles do I have to multiply it with: those of cell1 or those of cell1+cell2?)
I'm working on a MCNP simulation where I have to use F6 tallies. According to the manual: "In the F6 and +F6 tallies, material density is available for the chosen cells, and normalization is MeV/gm/source-particle."
To which source-particles is this value normalized: the source-particles in the chosen cell or the source-particles of the whole simulation?
(Example: Let's say I have two cells (cell1 and cell2) in the simulation, both tallied. If I would like to get cell1's MeV/gm energy density with which amount of source-particles do I have to multiply it with: those of cell1 or those of cell1+cell2?)