I tried to do a k-eigenvalue calculation to check whether my pebble design was successful, but when I tried to start the calculation an error appeared stating that " ERROR: More than 95% of sampled external source sites were rejected. Please check your external source spatial definition. " , what should I do to solve this problem?
##################################################### GEOMETRI #####################################################
## ********** (FUEL 1) **********
kernelsph = openmc.Sphere(r=0.025, boundary_type='reflective') #KERNEL
buffsph = openmc.Sphere(r=0.034, boundary_type='reflective') #BUFFER
IPyCsph = openmc.Sphere(r=0.038, boundary_type='reflective') #In PyC
SiCsph = openmc.Sphere(r=0.0423, boundary_type='reflective') #SiC
OPyCsph = openmc.Sphere(r=0.0463, boundary_type='reflective') #Out Pyc
kernel_cell = openmc.Cell(fill= fuel , region = -kernelsph ) #kernel
buffer_cell = openmc.Cell(fill= buffer , region = +kernelsph & -buffsph ) #buffer
IPyC_cell = openmc.Cell(fill= IPyC , region = +buffsph & - IPyCsph ) #Ipyc
SiC_cell = openmc.Cell(fill= SiC , region = + IPyCsph & -SiCsph ) #SiC
OPyC_cell = openmc.Cell(fill= OPyC , region = +SiCsph & -OPyCsph ) #OPyC
Triso_unv = openmc.Universe(cells=(kernel_cell,buffer_cell,IPyC_cell,SiC_cell,OPyC_cell)) #TRISO UNIVERSE
Triso_part = openmc.Cell(fill=Triso_unv, region=-OPyCsph) #TRISO CELL
# Pebble-bed Fuel 1
fuel_zone = openmc.Sphere(r=2.5, boundary_type='vacuum') #r_fuel zone
r_fuel_pebble = openmc.Sphere(r=3.0, boundary_type='vacuum') #r_fuel_pebble
triso_outer_radius = 0.0463 #outer_r_of triso particle
spheres = openmc.model.pack_spheres(radius=triso_outer_radius,num_spheres=8335, region=-fuel_zone, pf=0.5)
triso_particles = [openmc.model.TRISO(triso_outer_radius, fill=Triso_unv, center=c) for c in spheres]
lattice_fuel_zone_cell = openmc.Cell(region=-fuel_zone)
lower_left, upp_right = lattice_fuel_zone_cell.region.bounding_box
shape = (4, 4, 4)
pitch = (upp_right - lower_left)/shape
triso_latt = openmc.model.create_triso_lattice(triso_particles, lower_left, pitch, shape, in_graphite)
lattice_fuel_zone_cell.fill = triso_latt
lattice_universe = openmc.Universe(cells=[lattice_fuel_zone_cell])
## pebble fuel 1
fuel_pebble = openmc.Cell (fill = out_graphite , region = +fuel_zone & -r_fuel_pebble)
fuel_outer = openmc.Cell (fill = Coolant_He , region = +r_fuel_pebble)
fuel_pebble_unv = openmc.Universe (cells = [lattice_fuel_zone_cell,fuel_pebble,fuel_outer, ])
fuel_1 = openmc.Cell (fill= fuel_pebble_unv)
geometry =openmc.Geometry([fuel_pebble, ])
geometry.export_to_xml()
## settings
settings = openmc.Settings()
settings.batches = 300
settings.inactive = 50
settings.particles = 100000
bounds = [-3, -3, -3, 3, 3, 3]
uniform_dist = openmc.stats.Box(bounds[:3], bounds[3:], only_fissionable=True)
settings.source = openmc.source.Source(space=uniform_dist)
settings.export_to_xml()