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fusion-energy / neutronics-workshop

A workshop covering a range of fusion relevant analysis and simulations with OpenMC, DAGMC, Paramak and other open source fusion neutronics tools
MIT License
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Adding regular mesh based shut down dose rate example #258

Open shimwell opened 7 months ago

shimwell commented 7 months ago

Not ready yet but this PR aims to add a mesh based R2S shut down dose rate simulation to the examples. There are a few more parts that need to be added to openmc before this PR can be finished. Currently the meshes that contain two or more materials are not modelled correctly

shimwell commented 3 months ago

Paul has a nice PR that solves the multiple materials on a single mesh voxel problem.

https://github.com/openmc-dev/openmc/pull/2971

usage is list_of_MIXED_materials_one_for_each_voxel = mesh_void.get_homogenized_materials(model, n_samples=1_000_000)

so it should be possible for me to finish of this example now

@rlbarker fyi

shimwell commented 2 months ago

The recent improvements in openmc reduce the complexity of this time of simulation considerably many thanks to @paulromano

I've tidied up the example and it is more concise but it is still not quite ready for use yet, sorry @rlbarker

Either I have made a mistake with my meshes or there is an openmc bug that when using a mesh source and a mesh tally then they both end up using the same mesh instead of different meshes. In this case I've got two meshes and want to make the source on a course regularmesh and tally the dose on a finer regular mesh but it appears to be using just the one mesh. I can look into this more.

shimwell commented 2 months ago

we will need the features in this PR as well https://github.com/openmc-dev/openmc/pull/3000