At present, I am performing decay calculations for spent fuel for long time periods (hundreds to thousands of years) using the compositions from the NEA benchmark on BUC-Phase VII, and I am using SERPENT2 as a decay code with the options 'decstep' or 'dectot' as coupled flux calculations are not needed.
The initial spent fuel composition contains isotopes for which there is no XS information, e.g. C-14, so SERPENT2 stops with the message like:
I do not know if it is already possible, but it would be interesting to include the possibility of letting decay and track also this isotopes for which there is no XS information but that could be important for other purposes (public dose in the benchmark) and be present in an initial fuel composition. I would propose some indication in the material definition that the isotope should not be considered in the transport calculation, but only during the decay calculation. So the fix can be applied either in burnup or only decay calculations, therefore in any situation and will make SERPENT2 also a more complete decay code.Nuclide 6014.03c not found in data libraries
I suppose a way around is to create fake XS data files for those isotopes and the code probably will run also. Is that a possible partial solution with SERPENT2? Do you have another way around?