WARNING: Negative value(s) found on probability table for nuclide Cs136 at 250K

The first question was answered here:

It’s important for OpenMC to know the correct volume of burnable materials for a depletion problem. If the volume is wrong, your results will be wrong too. Using a stochastic volume calculation seems like a good approach for this – what error are you seeing when you try running the stochastic volume calculation?