OpenMC for medicine physics computation

User Support
1

How to use OpenMC for radiation transport only? Because i want to calculate scattering dose from x-ray generator

2

For non-reactor applications, you would need to run a fixed source calculation. If you’re using the Python API, this can be done with:

settings = openmc.Settings()
settings.run_mode = ‘fixed source’

Then you need to create the source corresponding to your x-ray generator.

energy_dist = …
settings.source = openmc.Source(energy=energy_dist, particle=‘photon’)

where energy_dist is a one-dimensional distribution in energy (these can be created using classes out of the openmc.stats module). For more information about creating a source, see the user’s manual here.

Best,
Paul

3

Thanks a lot for your information, this is so helpful for me.

Pada Rabu, 24 Juni 2020 20.30.39 UTC+7, Paul Romano menulis:

4

Saya dari Palembang, senang mengetahui anda bisa berbahasa Indonesia :slight_smile: