From 88df2396b808f31d18b1564ada0fe92308bb2c8f Mon Sep 17 00:00:00 2001 From: Connor Moore Date: Wed, 22 Jul 2026 14:55:26 +0200 Subject: Added global tallies for absoprtion and fissison rates --- hpmr.py | 9 +++++++-- 1 file 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() -- cgit v1.2.3