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import materials_for_mc as m4mc # m4mc.Config.set_cross_sections({ # "Li6": "tendl-21", # "Li7": "tendl-21" # }) m4mc.Config.set_cross_sections("tendl-21") mat1 = m4mc.Material() mat1.add_element('Li', 0.5) mat1.set_density('g/cm3', 2.0) mat1.volume = 4.2 mat1.read_nuclides_from_json("tendl-21") print(mat1)