I’ve started writing an algorithm that uses the get_microxs_and_flux() functions to perform part of my calculations by a succession of static calculations and bateman resolution with homogeneous cross sections at 1G.
I’ve tried using a succession of get_microxs_and_flux and IndependantOperator, but I get the impression that it doesn’t solve the whole chain (especially without creation terms, if I’m not mistaken?). What’s more, I get the impression that it’s not possible to add a transfer_rate or source term, even though I’ve seen that this is the subject of a few PRs by adding a “source term”.
At the moment, I seem to have no choice but to build the bateman A matrix from scratch if I want to take a few transmutation steps with only flow renormalizations between macro-steps used to recalculate effective cross-sections.
Is this confirmed or have I missed something?
So, does transmutation have to be done by hand with an external solver (independent operator that doesn’t create nuclides from reactions?) or is there a way to use the solvers already present in openmc to make a totally internal application?
I get the impression that it doesn’t solve the whole chain (especially without creation terms, if I’m not mistaken?).
By default the IndependentOperator should be setting up tallies and solving for all nuclides in the provided chain. The capabilities in this object to reduce the chain are off by default. It’s possible that, depending on the nuclear data being used, some of the nuclides in the chain don’t have data to compute reaction rates but this happens pretty rarely (if ever?) for the decay chains we provide.
Can you expand on what you mean by “without creation terms”?
What’s more, I get the impression that it’s not possible to add a transfer_rate or source term, even though I’ve seen that this is the subject of a few PRs by adding a “source term”.
Correct, it is not yet possible to add custom transfer rates to depletion calculations. the PR adding this capability is still in review here
It was an impression, but I thought that the effective sections were used for the “destruction” of the nuclide, but there was no creation of the isotope.
For example, Fe56 will absorb and be deduced, but (taking an n,gamma) Fe57 will not be created. But I’m probably wrong about that.
I had done some manipulations on the chain and the isotopes were probably absent, hence the fact that they were not created.
Do you have any details on how I can extract my burnup matrix (if that’s possible)?