MCNP6.2 - Are results of FMESH tallies already divided by cell volume?

In summary, the FMESH tally results are already divided by the cell volume, as shown by the comparison with an F4 tally and the availability of the "out=cf" option. This is similar to TMESH where the average fluence is calculated by multiplying the particle weight by the track length and dividing by the volume. Although not explicitly stated in the MCNP manual, the FMESH calculation includes a division by the mesh cell volume, not the geometry cell. Therefore, the F4 and FMESH cell tallies should match if the geometry cell and mesh cell are coincident.
  • #1
19matthew89
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It's not clear whether the results of mesh tally for FMESH are already divided by the cell volume
Hi everyone,

I am struggling to understand whether the results of FMESH tallies are already divided by the cell volume or not.

I'd actually expect so considering:
1. the comparison with an F4 tally in the same cell where results are comparable only if I assume that the mesh tallies results are already divided by the cell volume
2. the fact that the option "out=cf" is available. With this option "the volume and the tally results multiplied by the volume are also printed". And so it would make sense multiplying the standard tally results by the volume only if its standard output were already divided by the volume
3. for "similarity" with TMESH, where indeed "average fluence is particle weight times track length divided by volume in units of number/cm2"

But I could not find anywhere in MCNP manual (MCNP® Code Version 6.3.0 Theory & User Manual) a clear statement about it.

Could you confirm, please?

Thanks in advance
 
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  • #2
The FMESH calculation includes a division by the mesh cell volume, not the geometry cell.

So if you had a geometry cell and a mesh cell that were totally coincident you'd expect the F4 and the FMESH cell tally to match.
 
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  • #3
Alex A said:
The FMESH calculation includes a division by the mesh cell volume, not the geometry cell.

So if you had a geometry cell and a mesh cell that were totally coincident you'd expect the F4 and the FMESH cell tally to match.
Great! Thanks!
 

1. What is MCNP6.2?

MCNP6.2 is a Monte Carlo N-Particle transport code used for simulating and analyzing the transport of particles through matter. It is widely used in the nuclear engineering and radiation physics fields.

2. What is an FMESH tally in MCNP6.2?

An FMESH tally in MCNP6.2 is a type of tally that calculates the flux or fluence of particles at specific mesh points in a geometry. It is useful for obtaining detailed spatial information about the particle transport in a system.

3. Are the results of FMESH tallies in MCNP6.2 already divided by cell volume?

Yes, the results of FMESH tallies in MCNP6.2 are already divided by cell volume. This is done to account for the variations in cell sizes and ensure accurate results.

4. Why is it important to divide FMESH tallies by cell volume in MCNP6.2?

Dividing FMESH tallies by cell volume in MCNP6.2 is important because it helps to normalize the results and account for any variations in cell sizes. This ensures that the results are accurate and can be compared across different cell geometries.

5. Can the division by cell volume be turned off for FMESH tallies in MCNP6.2?

Yes, the division by cell volume can be turned off for FMESH tallies in MCNP6.2 by setting the appropriate flag in the input file. However, it is generally recommended to keep this division on to ensure accurate and consistent results.

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