Earlier to get the score results for all the materials present in a cell “all” keyword was working fine. In the version 0.14.0 it returns ‘std::runtime_error’ with message ‘what(): Nuclide ‘all’ is not present in library.’
@arindam welcome to the community! You are correct that in prior versions of OpenMC, there used to be a special keyword where you could ask for “all” nuclides. We ended up removing this at some point because the same effect can be achieved relatively easily in Python with something like:
mat = openmc.Material()
mat.add_nuclide(...)
...
tally = openmc.Tally()
tally.scores = ...
tally.nuclides = mat.get_nuclides()
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