import matplotlib.pyplot as plt
from materials import *
import openmc

###############################################################################
#k eigenvalue simulation on msre (all safety rods fully inserted)
###############################################################################

h5m_filepath = 'h5m_files/msre.h5m'

#Materials
define_materials()

#geometry
graveyard=openmc.Sphere(r=10000,boundary_type='vacuum')

cad_univ = openmc.DAGMCUniverse(filename=h5m_filepath,auto_geom_ids=True,universe_id=996 )

cad_cell = openmc.Cell(cell_id=997 , region= -graveyard, fill= cad_univ)

root = openmc.Universe(universe_id=998)
root.add_cells([cad_cell])
geometry = openmc.Geometry(root)
geometry.export_to_xml()

settings = openmc.Settings()
settings.temperature = {'method':'interpolation'}
settings.batches = 100
settings.inactive = 10
settings.particles = 10000
settings.max_lost_particles = 10000
source_area = openmc.stats.Box([-200., -200., -200.],[ 200.,  200.,  200.],only_fissionable = True)
settings.source = openmc.Source(space=source_area)
settings.export_to_xml()

openmc.run()