Deterministic neutron transport in FUSE

Project.toml

@@ -24,6 +24,9 @@ Fortran90Namelists = "8fb689aa-71ff-4044-8071-0cffc910b57d"
 ForwardDiff = "f6369f11-7733-5829-9624-2563aa707210"
 FusionMaterials = "4c86da02-02c8-4634-8460-96566129f8e0"
 GeoInterface = "cf35fbd7-0cd7-5166-be24-54bfbe79505f"
+Gridap = "56d4f2e9-7ea1-5844-9cf6-b9c51ca7ce8e"
+GridapGmsh = "3025c34a-b394-11e9-2a55-3fee550c04c8"
+HDF5 = "f67ccb44-e63f-5c2f-98bd-6dc0ccc4ba2f"
 IMAS = "13ead8c1-b7d1-41bb-a6d0-5b8b65ed587a"
 IMASDD = "06b86afa-9f21-11ec-2ef8-e51b8960cfc5"
 InteractiveUtils = "b77e0a4c-d291-57a0-90e8-8db25a27a240"
@@ -41,6 +44,7 @@ Metaheuristics = "bcdb8e00-2c21-11e9-3065-2b553b22f898"
 MillerExtendedHarmonic = "c82744c2-dc08-461a-8c37-87ab04d0f9b8"
 NLsolve = "2774e3e8-f4cf-5e23-947b-6d7e65073b56"
 NNeutronics = "a9424c20-d414-11ec-167b-9106c24d956c"
+NeutronTransport = "161f4978-d3bb-4696-90f4-058341551711"
 NumericalIntegration = "e7bfaba1-d571-5449-8927-abc22e82249b"
 Optim = "429524aa-4258-5aef-a3af-852621145aeb"
 OrderedCollections = "bac558e1-5e72-5ebc-8fee-abe8a469f55d"
@@ -52,13 +56,18 @@ ProgressMeter = "92933f4c-e287-5a05-a399-4b506db050ca"
 QED = "8bcbec86-48c7-11ec-16a6-c1bc83299373"
 QuadGK = "1fd47b50-473d-5c70-9696-f719f8f3bcdc"
 Random = "9a3f8284-a2c9-5f02-9a11-845980a1fd5c"
+RayTracing = "3007c720-8091-40db-9339-e09e4eb4c7ea"
+Reexport = "189a3867-3050-52da-a836-e630ba90ab69"
+Setfield = "efcf1570-3423-57d1-acb7-fd33fddbac46"
 SimulationParameters = "32ab26d3-25d6-405d-a295-367385e16093"
 SnoopPrecompile = "66db9d55-30c0-4569-8b51-7e840670fc0c"
 SpecialFunctions = "276daf66-3868-5448-9aa4-cd146d93841b"
+StaticArrays = "90137ffa-7385-5640-81b9-e52037218182"
 TAUENN = "4f5ffc88-c87f-11eb-142e-4d2ba0394a67"
 TEQUILA = "a60c9cbd-e72f-4185-96b6-b8fc312c4d37"
 TGLFNN = "558c7b13-fd9f-4806-b461-592296cfa9d0"
 TimerOutputs = "a759f4b9-e2f1-59dc-863e-4aeb61b1ea8f"
+UnPack = "3a884ed6-31ef-47d7-9d2a-63182c4928ed"
 VacuumFields = "9d9223b5-c5da-4bf4-abee-2a8bb6775a49"
 Weave = "44d3d7a6-8a23-5bf8-98c5-b353f8df5ec9"
 

playground/2d_neutron_transport_example.ipynb

@@ -0,0 +1,90 @@
+{
+ "cells": [
+  {
+   "cell_type": "code",
+   "execution_count": null,
+   "id": "a1c50669",
+   "metadata": {},
+   "outputs": [],
+   "source": [
+    "using Revise\n",
+    "using FUSE"
+   ]
+  },
+  {
+   "cell_type": "code",
+   "execution_count": null,
+   "id": "009f8417",
+   "metadata": {},
+   "outputs": [],
+   "source": [
+    "ini, act = FUSE.case_parameters(:FPP; version=:v1_demount, init_from=:scalars);\n",
+    "dd = FUSE.init(ini, act; do_plot=false);"
+   ]
+  },
+  {
+   "cell_type": "code",
+   "execution_count": null,
+   "id": "02231999",
+   "metadata": {},
+   "outputs": [],
+   "source": [
+    "data_path=\"/fusion/projects/ird/ptp/mclaughlink/\"\n",
+    "data_filename=\"combined_mgxs_lib.h5\""
+   ]
+  },
+  {
+   "cell_type": "code",
+   "execution_count": null,
+   "id": "7f81ec0c",
+   "metadata": {},
+   "outputs": [],
+   "source": [
+    "@time sol = FUSE.neutron_transport_2d(dd, data_path, data_filename)"
+   ]
+  },
+  {
+   "cell_type": "code",
+   "execution_count": null,
+   "id": "a6195600",
+   "metadata": {},
+   "outputs": [],
+   "source": [
+    "FUSE.get_tbr(sol, dd, data_path, data_filename)"
+   ]
+  },
+  {
+   "cell_type": "code",
+   "execution_count": null,
+   "id": "e6d8682a",
+   "metadata": {},
+   "outputs": [],
+   "source": [
+    "FUSE.write_neutron_flux_vtk(sol)"
+   ]
+  },
+  {
+   "cell_type": "markdown",
+   "id": "931b8a69",
+   "metadata": {},
+   "source": [
+    "You can now use Paraview or a similar program to view the fluxes.vtu file. If running on Omega, you can type `/fusion/projects/codes/neutronics/ParaView-5.11.1-MPI-Linux-Python3.9-x86_64/bin/paraview` in your terminal window to launch Paraview."
+   ]
+  }
+ ],
+ "metadata": {
+  "kernelspec": {
+   "display_name": "Julia 1.9.2",
+   "language": "julia",
+   "name": "julia-1.9"
+  },
+  "language_info": {
+   "file_extension": ".jl",
+   "mimetype": "application/julia",
+   "name": "julia",
+   "version": "1.9.2"
+  }
+ },
+ "nbformat": 4,
+ "nbformat_minor": 5
+}

playground/neutron_transport_example.ipynb

@@ -0,0 +1,101 @@
+{
+ "cells": [
+  {
+   "cell_type": "code",
+   "execution_count": null,
+   "metadata": {},
+   "outputs": [],
+   "source": [
+    "using Revise\n",
+    "using FUSE"
+   ]
+  },
+  {
+   "cell_type": "markdown",
+   "metadata": {},
+   "source": [
+    "Build an arbitrary 1D geometry using `FUSE.concentric_cylinders()`"
+   ]
+  },
+  {
+   "cell_type": "code",
+   "execution_count": null,
+   "metadata": {},
+   "outputs": [],
+   "source": [
+    "layer_thicknesses =  [100, 0.5,20,1]  # eventually replace with dd.build.layer.ΔR ?\n",
+    "material_names = [\"DT_plasma\", \"Tungsten\", \"lithium-lead-Li6enrich=90\",\"eurofer\"] # eventually replace with dd.build.layer.material\n",
+    "layers = [\"plasma\", \"First Wall\", \"Breeder\", \"Back wall\"]\n",
+    "mat_tags = Dict(zip(layers, material_names))\n",
+    "data_path = \"/fusion/projects/ird/ptp/mclaughlink/\"\n",
+    "data_filename= \"combined_mgxs_lib.h5\"\n",
+    "save_path = data_path\n",
+    "save_filename = \"concentric_circles\"\n",
+    "sol = FUSE.concentric_circles(layer_thicknesses, material_names, layers, data_path, data_filename, save_path, save_filename)"
+   ]
+  },
+  {
+   "cell_type": "code",
+   "execution_count": null,
+   "metadata": {},
+   "outputs": [],
+   "source": [
+    "tbr = FUSE.get_tbr(sol, mat_tags, data_path, data_filename)"
+   ]
+  },
+  {
+   "cell_type": "markdown",
+   "metadata": {},
+   "source": [
+    "Or, to build a 1D simulation based on FUSE's midplane layer thicknesses, use `FUSE.neutron_transport_1d()`:"
+   ]
+  },
+  {
+   "cell_type": "code",
+   "execution_count": null,
+   "metadata": {},
+   "outputs": [],
+   "source": [
+    "ini, act = FUSE.case_parameters(:FPP; version=:v1_demount, init_from=:scalars);\n",
+    "dd = FUSE.init(ini, act; do_plot=false);"
+   ]
+  },
+  {
+   "cell_type": "code",
+   "execution_count": null,
+   "metadata": {},
+   "outputs": [],
+   "source": [
+    "sol = FUSE.neutron_transport_1d(dd, data_path, data_filename)"
+   ]
+  },
+  {
+   "cell_type": "code",
+   "execution_count": null,
+   "metadata": {},
+   "outputs": [],
+   "source": [
+    "tbr = FUSE.get_tbr(sol, dd, data_path, data_filename)"
+   ]
+  }
+ ],
+ "metadata": {
+  "@webio": {
+   "lastCommId": null,
+   "lastKernelId": null
+  },
+  "kernelspec": {
+   "display_name": "Julia (10 threads) 1.9.0",
+   "language": "julia",
+   "name": "julia-_10-threads_-1.9"
+  },
+  "language_info": {
+   "file_extension": ".jl",
+   "mimetype": "application/julia",
+   "name": "julia",
+   "version": "1.9.0"
+  }
+ },
+ "nbformat": 4,
+ "nbformat_minor": 2
+}

src/FUSE.jl

@@ -62,6 +62,7 @@ include(joinpath("actors", "build", "cx_actor.jl"))
 
 include(joinpath("actors", "nuclear", "blanket_actor.jl"))
 include(joinpath("actors", "nuclear", "neutronics_actor.jl"))
+include(joinpath("actors", "nuclear", "neutron_transport_actor.jl"))
 
 include(joinpath("actors", "current", "qed_actor.jl"))
 include(joinpath("actors", "current", "steadycurrent_actor.jl"))