Hi OpenMC team,
I’m working on a fixed-source photon transport simulation to evaluate Bremsstrahlung radiation from Sr-90/Y-90 decay. The geometry is imported from a DAGMC file (ARTEMIS_DAGMC_Symmetry_CM.h5m), and the simulation uses photon transport with a spatial source defined inside a cylindrical SrTiO₃ fuel region.
To model the Bremsstrahlung spectrum, I used a discrete energy distribution derived from a radiation yield curve (yield per energy bin).
I’m using a mesh tally with a mesh filter, photon filter, and an energy function filter based on ICRP 116 AP dose coefficients. The tally uses the ‘flux’ score to estimate dose.
After scaling the results to μSv/hr using a realistic source activity and number of simulated particles, the calculated dose values are extremely high—several Sv/hr in some voxels—which seems unphysical.
I suspect the issue may be related to the tally setup or how I’m scaling the results. I’d appreciate any guidance on how to properly define and interpret dose tallies in this context.
Thank you,
Yuliia