import materials_for_mc as m4mc
m4mc.Config.set_cross_sections({
"Be9": "tests/Be9.json",
"Fe54": "tests/Fe54.json",
"Fe56": "tests/Fe56.json",
"Fe57": "tests/Fe57.json",
"Fe58": "tests/Fe58.json",
"Li6": "tests/Li6.json",
"Li7": "tests/Li7.json",
})
mat1 = m4mc.Material()
mat1.add_nuclide('Li6', 0.5)
mat1.add_nuclide('Li7', 0.5)
mat1.add_nuclide('Fe56', 1.0)
mat1.add_nuclide('Be9', 1.0)
mat1.set_density('g/cm3', 2.0)
print(mat1)
xs, energy = mat1.macroscopic_cross_section(reaction='(n,gamma)')
xs, energy = mat1.macroscopic_cross_section(reaction=1)
print(xs)