When using openmc.lib.init() this would load up the nuclear data in the materials and then you can add to this collection with openmc.lib.load_nuclide.
Also another option to speed up the cross section loading is to use parallel hdf5
Slightly related but you might be keen to hear that we recently removed the need to load cross sections when plotting and also there is a live pull request that removes the need to load cross sections when doing a stocatisc volume calculation.
For this example the nuclear data now gets loaded just once instead of 5 times which saves a decent amount of time as the simulation itself is very quick
That looks perfect, thanks! I’ll have a look at this and see if I can make use of it. Sorry for the slow replies, struggling to find time for my side project