From cc7424a556fbd79e0c3e7b82b48ed25f7e6f131b Mon Sep 17 00:00:00 2001 From: shimwell Date: Wed, 15 Nov 2023 23:37:23 +0000 Subject: [PATCH] typos --- .../1_cell_based_shut_down_dose_rate_example.py | 4 ++-- 1 file changed, 2 insertions(+), 2 deletions(-) diff --git a/tasks/task_11_CSG_shut_down_dose_tallies/1_cell_based_shut_down_dose_rate_example.py b/tasks/task_11_CSG_shut_down_dose_tallies/1_cell_based_shut_down_dose_rate_example.py index 0abc19e2..5f5b2a51 100644 --- a/tasks/task_11_CSG_shut_down_dose_tallies/1_cell_based_shut_down_dose_rate_example.py +++ b/tasks/task_11_CSG_shut_down_dose_tallies/1_cell_based_shut_down_dose_rate_example.py @@ -198,7 +198,7 @@ # one should also fill the cells with the activated material - # the activated material contains ALL the iotopes produced during activation + # the activated material contains ALL the nuclides produced during activation # sphere_cell_2.fill = results[i_cool].get_material("1") # sphere_cell_3.fill = results[i_cool].get_material("2") # my_geometry = openmc.Geometry([sphere_cell_1, sphere_cell_2, sphere_cell_3]) @@ -207,7 +207,7 @@ # so you could make use of openmc.deplete.Results.export_to_materials to export the modified activated material that # just contains isotopes that appear in your cross_sections.xml - # however in this example we just use the original prisine material my_materials that were cloned earlier + # however in this example we just use the original pristine material my_materials that were cloned earlier # my_geometry is also the same as the neutron simulation pristine_mat_iron.id = 1 pristine_mat_aluminium.id =2