From 50211d4c8a2f659ef5b5c31c3efc529eaddc588a Mon Sep 17 00:00:00 2001
From: Jonathan Shimwell <mail@jshimwell.com>
Date: Fri, 29 Mar 2024 18:05:09 +0000
Subject: [PATCH] lib

---
 .../6_unstructured_mesh_source.py             | 96 ++++++++-----------
 1 file changed, 38 insertions(+), 58 deletions(-)

diff --git a/tasks/task_04_make_sources/6_unstructured_mesh_source.py b/tasks/task_04_make_sources/6_unstructured_mesh_source.py
index b42d7f2..bded620 100644
--- a/tasks/task_04_make_sources/6_unstructured_mesh_source.py
+++ b/tasks/task_04_make_sources/6_unstructured_mesh_source.py
@@ -1,10 +1,12 @@
-# from cad_to_dagmc import CadToDagmc
+from cad_to_dagmc import CadToDagmc
 
-# my_model = CadToDagmc()
+my_model = CadToDagmc()
 
-# my_model.add_stp_file('plasma_simplified_180.step')   
+my_model.add_stp_file('plasma_simplified_180.step')   
+# import gmsh
+# gmsh.initialize()
 
-# my_model.export_unstructured_mesh_file(filename="umesh.h5m", max_mesh_size=100, min_mesh_size=10)
+gmshm = my_model.export_unstructured_mesh_file(filename="umesh.h5m", max_mesh_size=100, min_mesh_size=10)
 
 # perhaps trimesh can get volumes
 # import trimesh
@@ -13,82 +15,60 @@
 
 
 import openmc
+import openmc.lib
 
 openmc.config['cross_sections'] = '/home/j/endf-b8.0-hdf5/endfb-viii.0-hdf5/cross_sections.xml'
 
 umesh = openmc.UnstructuredMesh(filename="umesh.h5m",library='moab')
 
-####
-
-mesh_filter = openmc.MeshFilter(umesh)
-tally = openmc.Tally(name="unstrucutred_mesh_tally")
-tally.filters = [mesh_filter]
-tally.scores = ["flux"]
-tally.estimator = "tracklength"
-my_tallies = openmc.Tallies([tally])
-
-mat1 = openmc.Material()
-mat1.add_nuclide("H1", 1, percent_type="ao")
-mat1.set_density("g/cm3", 0.001)
-my_materials = openmc.Materials([mat1])
-
 surf1 = openmc.Sphere(r=50000, boundary_type="vacuum")
 region1 = -surf1
 
 cell1 = openmc.Cell(region=region1)
-cell1.fill = mat1
 
 my_geometry = openmc.Geometry([cell1])
 
-my_settings = openmc.Settings()
-my_settings.batches = 1
-my_settings.inactive = 0
-my_settings.particles = 1
-my_settings.run_mode = "fixed source"
-
-# Create a DT point source
 my_source = openmc.IndependentSource()
 my_source.space = openmc.stats.Point((0, 0, 0))
 my_source.angle = openmc.stats.Isotropic()
 my_source.energy = openmc.stats.Discrete([14e6], [1])
-my_settings.source = my_source
-
-model = openmc.model.Model(my_geometry, my_materials, my_settings, my_tallies)
-sp_filename = model.run()
 
-sp = openmc.StatePoint(sp_filename)
+all_sources = [my_source] * 1767
+mesh_source = openmc.MeshSource(
+    mesh=umesh,
+    sources=all_sources,
+)
 
-tally_result = sp.get_tally(name="unstrucutred_mesh_tally")
+my_settings = openmc.Settings()
+my_settings.batches = 1
+my_settings.particles = 1
+my_settings.run_mode = "fixed source"
+my_settings.source = mesh_source
 
-# normally with regular meshes I would get the mesh from the tally
-# but with unstrucutred meshes the tally does not contain the mesh
-# however we can get it from the statepoint file
-# umesh = tally_result.find_filter(openmc.MeshFilter)
-umesh_from_sp = sp.meshes[1]
+model = openmc.model.Model(my_geometry, None, my_settings )
+model.export_to_model_xml()
 
-# these trigger internal code in the mesh object so that its centroids and volumes become known.
-# centroids and volumes are needed for the get_values and write_data_to_vtk steps
-centroids = umesh_from_sp.centroids
-mesh_vols = umesh_from_sp.volumes
+openmc.lib.init()
+# umesh_full = openmc.lib.meshes[umesh.id]
+# openmc.lib.UnstructuredMesh()
 
-#### end of code needed due to umesh not loading
 
-all_sources = []
-all_strengths = []
-for volume, centroid in zip(centroids, mesh_vols):
-    my_source = openmc.IndependentSource()
-    my_source.angle = openmc.stats.Isotropic()
-    # the energy could be based on location of centroid
-    my_source.energy = openmc.stats.Discrete([14e6], [1])
-    # the energy could be based on location of centroid and volume
-    my_source.strength=1
-    all_strengths.append(mesh_vols)
+# all_sources = []
+# all_strengths = []
+# for volume, centroid in zip(centroids, mesh_vols):
+#     my_source = openmc.IndependentSource()
+#     my_source.angle = openmc.stats.Isotropic()
+#     # the energy could be based on location of centroid
+#     my_source.energy = openmc.stats.Discrete([14e6], [1])
+#     # the energy could be based on location of centroid and volume
+#     my_source.strength=1
+#     all_strengths.append(mesh_vols)
 
-mesh_source = openmc.MeshSource(
-    mesh=umesh,
-    sources=all_sources,
-)
+# mesh_source = openmc.MeshSource(
+#     mesh=umesh,
+#     sources=all_sources,
+# )
 
-mesh_source.normalize_source_strengths()
+# mesh_source.normalize_source_strengths()
 
-# https://github.com/fusion-energy/cad_to_dagmc/blob/main/examples/unstrucutred_volume_mesh/simulate_unstrucutred_volume_mesh_with_openmc.py
\ No newline at end of file
+# # https://github.com/fusion-energy/cad_to_dagmc/blob/main/examples/unstrucutred_volume_mesh/simulate_unstrucutred_volume_mesh_with_openmc.py
\ No newline at end of file