Added global tallies for absoprtion and fissison rates

1 files changed, 7 insertions, 2 deletions

diff --git a/hpmr.py b/hpmr.py
index ef818cc..5604974 100755
--- a/hpmr.py
+++ b/hpmr.py
@@ -688,7 +688,6 @@ geo_core_rad_lattice.universes=geo_core_rad_lattice_map
 geo_core_rad_cell=openmc.Cell(name="Core Radial Slice Cell",fill=geo_core_rad_lattice)
 geo_core_rad_universe = openmc.Universe(cells=[geo_core_rad_cell])
 
-
 # Axial Reflector lattice
 geo_core_rad_refl_lattice=openmc.HexLattice()
 geo_core_rad_refl_lattice.center=(0,0)
@@ -750,9 +749,15 @@ set_entropy_mesh.upper_right=(+set_dyn_radial,+set_dyn_radial,+set_dyn_axial)
 set_entropy_mesh.dimension=(30,30,30)
 
 settings.entropy_mesh=set_entropy_mesh
-
 settings.temperature = {'method': "interpolation"}
 
+############ TALLIES ############ 
+tal_global = openmc.Tally(name="Global Reaction Rate")
+tal_global.scores = ["absorption","fission"]
+
+tallies = openmc.Tallies([tal_global])
+tallies.export_to_xml()
+
 ## Export ##
 materials = openmc.Materials(mat_list)
 materials.export_to_xml()