done t2 and t3

fusion-energy · Sep 30, 2024 · c80667b · c80667b
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commit c80667b
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diff --git a/tasks/task_02_making_materials/2_example_materials_from_elements.ipynb b/tasks/task_02_making_materials/2_example_materials_from_elements.ipynb
@@ -15,7 +15,7 @@
    "cell_type": "markdown",
    "metadata": {},
    "source": [
-    "The following code block is a simple example of creating a material (water H2O) from elements. (Note how Hydrogen and Oxygen elements have been specified rather than each specific isotope)."
+    "First import OpenMC and configure the nuclear data path"
    ]
   },
   {
@@ -26,6 +26,24 @@
    "source": [
     "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'"
+   ]
+  },
+  {
+   "cell_type": "markdown",
+   "metadata": {},
+   "source": [
+    "The following code block is a simple example of creating a material (water H2O) from elements. (Note how Hydrogen and Oxygen elements have been specified rather than each specific isotope)."
+   ]
+  },
+  {
+   "cell_type": "code",
+   "execution_count": null,
+   "metadata": {},
+   "outputs": [],
+   "source": [
     "# Making water from elements\n",
     "\n",
     "water_mat = openmc.Material()\n",

diff --git a/tasks/task_02_making_materials/5_example_materials_mixed.ipynb b/tasks/task_02_making_materials/5_example_materials_mixed.ipynb
@@ -24,15 +24,25 @@
     "This python notebook allows users to make mixed materials using OpenMC and the Neutronics Material Maker."
    ]
   },
+  {
+   "cell_type": "markdown",
+   "metadata": {},
+   "source": [
+    "First import packages needed and configure the OpenMC nuclear data path"
+   ]
+  },
   {
    "cell_type": "code",
    "execution_count": null,
    "metadata": {},
    "outputs": [],
    "source": [
-    "# import the packages needed for the task\n",
+    "import neutronics_material_maker as nmm\n",
     "import openmc\n",
-    "import neutronics_material_maker as nmm"
+    "\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'"
    ]
   },
   {

diff --git a/tasks/task_03_making_CSG_geometry/1_simple_csg_geometry.ipynb b/tasks/task_03_making_CSG_geometry/1_simple_csg_geometry.ipynb
@@ -22,6 +22,26 @@
     "IFrame(src=\"https://www.youtube.com/embed/Ovr7oYukYRw\", width=560, height=340)"
    ]
   },
+  {
+   "cell_type": "markdown",
+   "metadata": {},
+   "source": [
+    "First import OpenMC and configure the nuclear data path"
+   ]
+  },
+  {
+   "cell_type": "code",
+   "execution_count": null,
+   "metadata": {},
+   "outputs": [],
+   "source": [
+    "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'"
+   ]
+  },
   {
    "attachments": {},
    "cell_type": "markdown",
@@ -38,8 +58,6 @@
    "metadata": {},
    "outputs": [],
    "source": [
-    "import openmc\n",
-    "\n",
     "# example surfaces\n",
     "inner_sphere_surface = openmc.Sphere(r=500)\n",
     "outer_sphere_surface = openmc.Sphere(r=600)\n",

diff --git a/tasks/task_03_making_CSG_geometry/2_intermediate_csg_geometry.ipynb b/tasks/task_03_making_CSG_geometry/2_intermediate_csg_geometry.ipynb
@@ -9,8 +9,33 @@
     "\n",
     "This python notebook allows users to build upon the geometry constructed in Part 1 by adding a center column to the model.\n",
     "\n",
-    "The center column requires a different surface type. OpenMC has several different surface types in addition to spheres. The documentation contains useful information on all surface types supported: https://openmc.readthedocs.io/en/stable/usersguide/geometry.html#surfaces-and-regions.\n",
+    "The center column requires a different surface type. OpenMC has several different surface types in addition to spheres. The documentation contains useful information on all surface types supported: https://openmc.readthedocs.io/en/stable/usersguide/geometry.html#surfaces-and-regions."
+   ]
+  },
+  {
+   "cell_type": "markdown",
+   "metadata": {},
+   "source": [
+    "First import OpenMC and configure the nuclear data path"
+   ]
+  },
+  {
+   "cell_type": "code",
+   "execution_count": null,
+   "metadata": {},
+   "outputs": [],
+   "source": [
+    "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'"
+   ]
+  },
+  {
+   "cell_type": "markdown",
+   "metadata": {},
+   "source": [
     "For the center column we will use a cylinder with Z axis orientation.\n",
     "\n",
     "The code block below shows how the center column can be defined."
@@ -22,8 +47,6 @@
    "metadata": {},
    "outputs": [],
    "source": [
-    "import openmc\n",
-    "\n",
     "# surfaces\n",
     "central_column_surface = openmc.ZCylinder(r=100) # note the new surface type\n",
     "inner_sphere_surface = openmc.Sphere(r=480)\n",

diff --git a/tasks/task_03_making_CSG_geometry/3_viewing_the_geometry_as_vtk.ipynb b/tasks/task_03_making_CSG_geometry/3_viewing_the_geometry_as_vtk.ipynb
@@ -24,6 +24,13 @@
     "This first code block recreates the simple reactor geometry seen in Part 2, but also assigns materials to each cell."
    ]
   },
+  {
+   "cell_type": "markdown",
+   "metadata": {},
+   "source": [
+    "First import OpenMC and configure the nuclear data path"
+   ]
+  },
   {
    "cell_type": "code",
    "execution_count": null,
@@ -32,6 +39,17 @@
    "source": [
     "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'"
+   ]
+  },
+  {
+   "cell_type": "code",
+   "execution_count": null,
+   "metadata": {},
+   "outputs": [],
+   "source": [
     "copper = openmc.Material()\n",
     "copper.set_density('g/cm3', 8.5)\n",
     "copper.add_element('Cu', 1.0)  # Note, percent_type does not have to be specified as material is 100% copper\n",