[HF] OpenMC as a high-fidelity solver

[drewejohnson]

Overview

Please describe the solver, in particular

• Where is this solver documented?
  docs.openmc.org
• How can the solver be obtained? This helps with installation and testing
  https://github.com/openmc-dev/openmc
• summary of transport capabilities (e.g. flexibility of tallies, homogenization, continuous energy or multi-group, etc.)
  High-quality MC code that can run both in CE and MG mode. Good support for tallies of various reactions, and with filters for materials / cells / nuclides, etc. No fission matrix as of the time of this writing
• summary of geometry modeling
  CSG

Development

• Are you willing to develop this interface? If not, do you know someone with the knowledge to do it? Please link them in the issue
  Yes.
• Will you (or the developer linked previously) help maintain it?
  Yes
• How can this be tested? Writing input files can be done w/o running the executable, but may be more error prone unless we can run the solver in the test environment
  Can be installed with conda or from source directly. Writing input files would surely work but with some of the same issues I've been seeing with the Serpent writer (test fails, materials aren't properly updated/reset, causing the test files to be differently only in a material id). Can also run the full sequence

[khurrumsaleem]

Hi @drewejohnson.

Your paper https://www.sciencedirect.com/science/article/pii/S0306454920308161 brought me here. Just wanted to ask if there is any progress on this issue.

Thanks and keep up the good work.

[drewejohnson]

@khurrumsaleem thank you for the kind words. Unfortunately there has not been any progress on this feature