added correct nuc data path

fusion-energy · Oct 17, 2024 · 692139d · 692139d
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diff --git a/tasks/task_10_activation_transmutation_depletion/2_example_tally_change_with_burnup.ipynb b/tasks/task_10_activation_transmutation_depletion/2_example_tally_change_with_burnup.ipynb
@@ -9,21 +9,47 @@
     "This example simulates the variation of a tally responce as a function of time. This particular tally is the tritium breeding ratio and this tends to decrease over time as the lithium gets burnt up by neutron irradiation"
    ]
   },
+  {
+   "cell_type": "markdown",
+   "id": "9256b063",
+   "metadata": {},
+   "source": [
+    "\n",
+    "First import OpenMC and configure the nuclear data paths"
+   ]
+  },
   {
    "cell_type": "code",
    "execution_count": null,
-   "id": "9f65541a-65d9-423b-99f4-aa21f6e6b017",
+   "id": "b8b5587a",
    "metadata": {},
    "outputs": [],
    "source": [
     "# remove any old files\n",
-    "!rm settings.xm model.xml materials.xml geometry.xml settings.xml model.xml\n",
+    "!rm settings.xm model.xml materials.xml geometry.xml settings.xml\n",
     "\n",
     "import openmc\n",
     "import openmc.deplete\n",
     "import math\n",
     "\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",
+    "# This chain file was downloaded using the download_endf_chain script that is included in the openmc_data package https://github.com/openmc-data-storage/openmc_data\\n\",\n",
+    "# this file tells openmc the decay paths between isotopes including probabilities of different routes and half lives\n",
+    "# To download this xml file you can run these commands\n",
+    "# pip install openmc_data\n",
+    "# download_endf_chain -d nuclear_data -r b8.0\n",
+    "openmc.config['chain_file'] = '/nuclear_data/chain-endf-b8.0.xml'"
+   ]
+  },
+  {
+   "cell_type": "code",
+   "execution_count": null,
+   "id": "9f65541a-65d9-423b-99f4-aa21f6e6b017",
+   "metadata": {},
+   "outputs": [],
+   "source": [
     "# MATERIALS\n",
     "\n",
     "mats = openmc.Materials()\n",
@@ -125,13 +151,6 @@
    "metadata": {},
    "outputs": [],
    "source": [
-    "# This chain file was downloaded using the download_endf_chain script that is included in the openmc_data package https://github.com/openmc-data-storage/openmc_data\\n\",\n",
-    "# this file tells openmc the decay paths between isotopes including probabilities of different routes and half lives\n",
-    "# To download this xml file you can run these commands\n",
-    "# pip install openmc_data\n",
-    "# download_endf_chain -d nuclear_data -r b8.0\n",
-    "# openmc.config['chain_file'] = '/nuclear_data/chain-endf-b8.0.xml'\n",
-    "\n",
     "operator = openmc.deplete.CoupledOperator(\n",
     "    model=model,\n",
     "    normalization_mode=\"source-rate\",  # set for fixed source simulation, otherwise defaults to fission simulation\n",

diff --git a/tasks/task_10_activation_transmutation_depletion/3_full_pulse_schedule.ipynb b/tasks/task_10_activation_transmutation_depletion/3_full_pulse_schedule.ipynb
@@ -31,22 +31,20 @@
     "# remove any old files\n",
     "!rm settings.xm model.xml materials.xml geometry.xml settings.xml\n",
     "\n",
+    "import matplotlib.pyplot as plt\n",
     "import openmc\n",
     "import openmc.deplete\n",
     "import math\n",
-    "import matplotlib.pyplot as plt"
-   ]
-  },
-  {
-   "cell_type": "code",
-   "execution_count": null,
-   "id": "f42c7e11-f514-4859-855f-873fb8f4026e",
-   "metadata": {},
-   "outputs": [],
-   "source": [
-    "# chain and cross section paths have been set on the docker image but you may want to change them\n",
-    "#openmc.config['chain_file']=path to chain file\n",
-    "#openmc.config['cross_sections']=path to cross_sections.xml"
+    "\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",
+    "# This chain file was downloaded using the download_endf_chain script that is included in the openmc_data package https://github.com/openmc-data-storage/openmc_data\\n\",\n",
+    "# this file tells openmc the decay paths between isotopes including probabilities of different routes and half lives\n",
+    "# To download this xml file you can run these commands\n",
+    "# pip install openmc_data\n",
+    "# download_endf_chain -d nuclear_data -r b8.0\n",
+    "openmc.config['chain_file'] = '/nuclear_data/chain-endf-b8.0.xml'"
    ]
   },
   {