Hi,
How can i extract gamma production cross section from openmc cross section data base (MT=202 reaction).
Hi,
How can i extract gamma production cross section from openmc cross section data base (MT=202 reaction).
Hello,
using the following code you can get reaction cross-sections.
import openmc
import matplotlib.pyplot as plt
from openmc.data.reaction import REACTION_NAME # if you want reaction names
XSdir = '/home/mark_wsl/xsdata/' # this will probably be diferent for you
library = 'FENDL-3.1d'
isotope = 'H1'
MT = 102
xs_filename = f'{XSdir}{library}_{isotope}.h5'
isotope_data = openmc.data.IncidentNeutron.from_hdf5(xs_filename)
reaction = isotope_data.reactions[MT]
xs = reaction.xs['300K']
x, y = xs.x, xs.y
plt.plot(x,y, label=f'{isotope} {REACTION_NAME[MT]}')
plt.xscale('log')
plt.yscale('log')
plt.xlabel(r'$E$ [eV]')
plt.ylabel(r'$\sigma$ [b]')
plt.legend()

Hope it helps!
Mark