I am specifying a few different tallies, and some of them work, while others do not.

When in the standard neutron only calculation mode, all of my tallies work as they are supposed to. These are specified as follows, where the first two are power and flux in a particular material, and the third is power over a lattice:

Code: Select all

```
det PowerBatch1Axial1 dm Batch1Axial1 dr -8 void
det FluxBatch1Axial1 dm Batch1Axial1
det AssemblyPowerAxial1 dl 1 dr -8 void
```

Code: Select all

```
det PowerBatch1Axial1 1 dm Batch1Axial1 dr -8 void
det FluxBatch1Axial1 1 dm Batch1Axial1
det AssemblyPowerAxial1 1 dl 1 dr -8 void
```

If I then turn the neutron/photon coupled mode back off and run the calc with the tallies specified as is (i.e. I keep in the "1" to specify neutrons), I get the same incorrect results, with zeros for the first and third tallies.

None of my trials caused the tally magnitude for the second (flux) tally to be zero. For some reason only the tallies which have response functions seem to be impacted.

I have also tried to include tallies of photons with response functions, and got zeros for all of these.

It appears that something might be wrong with the routine which reads in the tallies. Or perhaps the routine that prints out the tally results.