I am just starting my journey of working with OpenMC, and I want to simulate the Small Modular Reactors using this tool. I am writing to ask for your recommendations on where should I start from. What files do I need? Where to get the parameters from? Where can I find the examples of SMR codes?
Specifically, I plan to use OpenMC for neytron shielding materials optimization.
I already found papers on this topic, though it is hard for me to start actually coding.
First of all, welcome to OpenMC! Apologies for the delayed reply.
To get started, I highly recommend beginning with simple neutron shielding problems using OpenMC with Python. Work through the official examples and make sure you’ve installed the ENDF/B-VIII.0 HDF5 cross section data (essential for running simulations).
At this stage, it’s best to avoid jumping directly into full SMR core models — they’re quite complex.
The files you need include: material compositions, geometry, settings (source, particles, etc.), and nuclear data (ENDF, JEFF, etc.).
Keep in mind, there are no standard downloadable SMR input files or public SMR OpenMC models.
For materials and geometry, check handbooks, published studies, or IAEA data. For the neutron source, you can use Watt fission spectrum parameters, for example.