@@ -162,7 +162,8 @@ mat1.add_element('C', 0.05)
162162
163163mats = openmc.Materials([mat1])
164164
165- mats.download_cross_section_data(
165+ odd.download_cross_section_data(
166+ mats,
166167 libraries = [" FENDL-3.1d" ],
167168 set_OPENMC_CROSS_SECTIONS = True ,
168169 particles = [" neutron" ],
@@ -181,7 +182,8 @@ mat1.add_element('C', 0.05)
181182
182183mats = openmc.Materials([mat1])
183184
184- mats.download_cross_section_data(
185+ odd.download_cross_section_data(
186+ mats,
185187 libraries = [' ENDFB-7.1-NNDC' , ' TENDL-2019' ],
186188 set_OPENMC_CROSS_SECTIONS = True ,
187189 particles = [" neutron" ],
@@ -202,7 +204,8 @@ my_mat.add_s_alpha_beta('Be_in_BeO')
202204
203205mats = openmc.Materials([my_mat])
204206
205- mats.download_cross_section_data(
207+ odd.download_cross_section_data(
208+ mats,
206209 libraries = [' ENDFB-7.1-NNDC' , ' TENDL-2019' ],
207210 set_OPENMC_CROSS_SECTIONS = True ,
208211 particles = [" neutron" ],
@@ -221,7 +224,8 @@ mat1.add_element('C', 0.05)
221224
222225mats = openmc.Materials([mat1])
223226
224- mats.download_cross_section_data(
227+ odd.download_cross_section_data(
228+ mats,
225229 libraries = [' ENDFB-7.1-NNDC' , ' TENDL-2019' ],
226230 set_OPENMC_CROSS_SECTIONS = True ,
227231 particles = [" neutron" , " photon" ],
0 commit comments