Plotting the Neutron Flux Spectrum in OpenMC

Hello everyone
I am a beginner in OpenMC,
i don:t know how can I plot a neutron flux spectrum in OpenMC code, and what parameters are used (like EnergyFilter) to define it? Thank you.

Hi Dina, yes you should tallies several other parameters for neutron flux calculation. I will provide you the example for cylindrical mesh reactor but, you can always simplify, modify it or change it :slight_smile: .

All the best! and have fun.

Best regards,

Wazif.

neutronflux.py (5.7 KB)

Hi, check out the neutronics workshop if you haven’t already; it has great info & examples, I think there’s one in plotting flux spectrums: GitHub - 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 · GitHub