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   "source": [
    "# OpenMC Plotter demonstration\n",
    "\n",
    "Below is the definition of a PWR assembly model with three tallies for use in the live demonstration of the openmc-plotter GUI application. The boundary conditions on the PWR assembly are changed to vacuum boundaries so that the flux profile is not flat."
   ]
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       "PosixPath('/home/ubuntu/openmc-nea-course/notebooks/plotter/statepoint.100.h5')"
      ]
     },
     "execution_count": 1,
     "metadata": {},
     "output_type": "execute_result"
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   ],
   "source": [
    "import openmc\n",
    "import numpy as np\n",
    "\n",
    "model = openmc.examples.pwr_assembly()\n",
    "\n",
    "# change the boundries, to make it looks cosine, not flat\n",
    "for surf in model.geometry.get_all_surfaces().values():\n",
    "    if surf.boundary_type == 'reflective':\n",
    "        surf.boundary_type = 'vacuum'\n",
    "\n",
    "\n",
    "model.settings.particles = 10_000\n",
    "model.settings.batches = 100\n",
    "model.settings.inactive = 10\n",
    "\n",
    "# added a tally to see\n",
    "mesh = openmc.RegularMesh()\n",
    "mesh.lower_left = (-10.71, -10.71)\n",
    "mesh.upper_right = (10.71, 10.71)\n",
    "mesh.dimension = (100, 100)\n",
    "\n",
    "reg_mesh_tally = openmc.Tally()\n",
    "reg_mesh_tally.scores = ['flux', 'fission']\n",
    "reg_mesh_tally.filters = [openmc.MeshFilter(mesh)]\n",
    "\n",
    "cyl_mesh = openmc.CylindricalMesh(\n",
    "    [0., 3., 5., 7.],\n",
    "    [-100., 100.],\n",
    "    np.linspace(0, 2*np.pi, 30), # azimutal\n",
    "    origin=(3., 3., 0.) # offset to see how it looks\n",
    ")\n",
    "\n",
    "cyl_mesh_tally = openmc.Tally()\n",
    "cyl_mesh_tally.scores = ['flux', 'fission']\n",
    "cyl_mesh_tally.filters = [openmc.MeshFilter(cyl_mesh)]\n",
    "\n",
    "fuel_cell = model.geometry.get_all_material_cells()[1]\n",
    "\n",
    "distribcell_tally = openmc.Tally()\n",
    "distribcell_tally.scores = ['flux']\n",
    "distribcell_tally.filters = [openmc.DistribcellFilter(fuel_cell)]\n",
    "\n",
    "model.tallies = [reg_mesh_tally, cyl_mesh_tally, distribcell_tally]\n",
    "\n",
    "model.run(output=False)"
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   "cell_type": "markdown",
   "id": "36e9d5a0-63c3-4149-b195-e511c7244076",
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   "source": [
    "### Notes\n",
    "\n",
    "Need to download the openmc-plotter separate, pip install as well, need x11\n",
    "\n",
    "overlap can be run with openmc -g to see overlap of materials"
   ]
  }
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