While using openmc a lot for various purposes, I wondered if they were a solver using analytical solution for depletion in openmc. I think the answer is no, right ?
I mean an algorithm that solves the problem X’ = AX, with X, the isotope quanties vector and A, the mass transfer matrix (with flux, cross sections, decay constants etc…)
The main advantage of this solution is to replace Independant operators, when there is no flux variations and no external mass transfer (we can still use the analytical solution if the mass transfer is constant over time by solving X’ = AX + B) no need to use a complicated and possibly unstable solver to track nuclides quantity evolution.
Do you think it is an interesting capability to be developed ?