Merge pull request #316 from fusion-energy/fixing-last-halfday-worksh…

…op-task addined xs path to last task in half day workshop
fusion-energy · Feb 11, 2025 · 608d593 · 608d593
2 parents 8916ee9 + 5dc10d8
commit 608d593
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diff --git a/tasks/task_19_design_task/1_optimal_design.ipynb b/tasks/task_19_design_task/1_optimal_design.ipynb
@@ -17,7 +17,9 @@
     "\n",
     "I recommend plotting the cross sections before you make your choices.\n",
     "\n",
-    "The [example](https://github.com/fusion-energy/neutronics-workshop/blob/main/tasks/task_01_cross_sections/3_material_xs_plot.ipynb) for plotting cross sections might be useful."
+    "The [example](https://github.com/fusion-energy/neutronics-workshop/blob/main/tasks/task_01_cross_sections/3_material_xs_plot.ipynb) for plotting cross sections might be useful.\n",
+    "\n",
+    "First import OpenMC and configure the nuclear data path"
    ]
   },
   {
@@ -27,7 +29,11 @@
    "metadata": {},
    "outputs": [],
    "source": [
-    "import openmc"
+    "import openmc\n",
+    "\n",
+    "# Setting the cross section path to the correct location in the docker image.\n",
+    "# If you are running this outside the docker image you will have to change this path to your local cross section path.\n",
+    "openmc.config['cross_sections'] = '/nuclear_data/cross_sections.xml'\n"
    ]
   },
   {

diff --git a/tasks/task_19_design_task/1_optimal_design_with_hints.ipynb b/tasks/task_19_design_task/1_optimal_design_with_hints.ipynb
@@ -17,7 +17,9 @@
     "\n",
     "I recommend plotting the cross sections before you make your choices.\n",
     "\n",
-    "The [example](https://github.com/fusion-energy/neutronics-workshop/blob/main/tasks/task_01_cross_sections/3_material_xs_plot.ipynb) for plotting cross sections might be useful."
+    "The [example](https://github.com/fusion-energy/neutronics-workshop/blob/main/tasks/task_01_cross_sections/3_material_xs_plot.ipynb) for plotting cross sections might be useful.\n",
+    "\n",
+    "First import OpenMC and configure the nuclear data path"
    ]
   },
   {
@@ -27,7 +29,11 @@
    "metadata": {},
    "outputs": [],
    "source": [
-    "import openmc"
+    "import openmc\n",
+    "\n",
+    "# Setting the cross section path to the correct location in the docker image.\n",
+    "# If you are running this outside the docker image you will have to change this path to your local cross section path.\n",
+    "openmc.config['cross_sections'] = '/nuclear_data/cross_sections.xml'\n"
    ]
   },
   {