[Meta] Work order for remaining PRs/Issues for OpenMC support

[yardasol]

1. Cleanup reprocessing-related classes and code #160
2. Cleanup test suite #161
3. Depcode issues
   • Feature: Cleanup depcode.py and related files #162
   • Feature: Add machinery to specify depletion settings in the main input file. #176
   • Serpent material temps #178
   • [Bug]: DepcodeSerpent.get_nuc_name() fails with MCNP-style metastable nuc-codes. #171
4. Feature: Enable use of mpiexec flags when executing depletion codes via SaltProc #173
5. Feature: DepcodeOpenMC methods for starting simulation and writing/reading input files #133
6. Feature: Docs overhaul #109
7. Cleanup Simulation class and related code, [Bug]: Use of "isotope" instead of "nuclide" in code, comments, and docs #120, [Bug]: PEP 257 enforcment #93, Feature: Reorder Depcode functions and make appropriate functions private #180
8. Feature: Consolidate nuclide name and code processing functions #191

[khurrumsaleem]

Hi,

@yardasol I just wanted to ask that can we use OpenMC as depletion code now or still have to wait for release of 0.5.0.?

Secondly will it be possible for you to add an example in examples folder for using OpenMC ad depletion code.

Thanks

[yardasol]

@khurrumsaleem OpenMC support will be available once 0.5.0 is released. An example case will be included in the release

[khurrumsaleem]

Thanks @yardasol

[yardasol]

@khurrumsaleem There will most likely be a prerelease once item 5 is finished. This is to have a reference-able version for my Master's thesis. The rest of the features will be competed after the thesis is submitted.

[yardasol]

@khurrumsaleem There is a pre-release of v0.5.0 that should be have fully functional OpenMC support. Please check it out and let me know what you think!

[yardasol]

All of these are done!