OpenMC Python API inputs: FNS Clean Benchmarks on W, V, Be

[Ebiwonjumi]

Hi Ethan,

I pushed some OpenMC inputs for fns clean benchmarks I have finished working on to a new branch. I will add a readme file soon.
I will also add inputs for Iron and Copper when I finish debugging them. Although I will kind of put these on hold and work on the UQ_SA review for now. Please let me know if there's some problem or anything wrong with the inputs.

Best,
Bamidele

[SteSeg]

Hi Bamidele, I was having a look at your paper and I read there is a slight discrepancy on the C/E values of the tungsten case study. I saw that even though the jaeri report gives one type of tungsten (actually a WNiCu alloy) with a given composition, the MCNP input file models two type of WNiCu with compositions different from the report and slightly different densities. The MCNP materials have ~10% less W, which is a rather good fast neutron reflector and might be the cause of a higher flux. Have you already had the chance of investigating this?

[Ebiwonjumi]

Hi Stefano. Right, I am using the the tungsten composition given in the JAERI report and I'm using the mcnp-w.inp (not REALISTIC) input from SINBAD. Also, two slightly different W densities are mixed inside each of the MCNP input files. However, OpenMC and MCNP gave similar spectra and MCNP also had similar discrepancies compared to experiment. So, it thus appear this is not the cause.
P.S. Compared to OpenMC, MCNP has slightly higher neutron flux in the vanadium/beryllium assemblies.
see attached

MIT_PSFC_Neutronics_Meeting_01312023_git.pptx.pdf
file