I used to be able to run the simulation and complete it in the previous version. But after 0.12.1 update (I have to update to do the couple physic simulation) this error prevent me from running
====================> K EIGENVALUE SIMULATION <====================
Bat./Gen. k Average k
========= ======== ====================
WARNING: Particle 830 had a negative distance to a lattice boundary
WARNING: Particle 525 had a negative distance to a lattice boundary
WARNING: Particle 469 had a negative distance to a lattice boundary
WARNING: Particle 80 had a negative distance to a lattice boundary
WARNING: Particle 609 had a negative distance to a lattice boundary
WARNING: Particle 849 had a negative distance to a lattice boundary
WARNING: Particle 914 had a negative distance to a lattice boundary
WARNING: Particle 360 had a negative distance to a lattice boundary
WARNING: Particle 44 had a negative distance to a lattice boundary
WARNING: Particle 90 had a negative distance to a lattice boundary
WARNING: Particle 922 had a negative distance to a lattice boundary
ERROR: Maximum number of lost particles has been reached.
This is how i define my lattice
fuel_or = openmc.ZCylinder(r=0.2965)
clad_ir = openmc.ZCylinder(r=0.3020)
clad_or = openmc.ZCylinder(r=0.3620)
fuel_region = -fuel_or
gap_region = +fuel_or & -clad_ir
clad_region = +clad_ir & -clad_or
water_region = +clad_or
#Fuel Cell for pin
fuel_cell_11 = openmc.Cell()
fuel_cell_11.fill = FUEL1
fuel_cell_11.region = fuel_region
gap_cell_11 = openmc.Cell()
gap_cell_11.region = gap_region
clad_cell_11 = openmc.Cell()
clad_cell_11.fill = cladb
clad_cell_11.region = clad_region
water_cell_11 = openmc.Cell()
water_cell_11.fill = waterLF1
water_cell_11.region = water_region
#Pin
pin11_universe = openmc.Universe(name='Lower Fissile 1 Pin',universe_id=711)
pin11_universe.add_cells((fuel_cell_11, gap_cell_11 , clad_cell_11 , water_cell_11))
#Water Cell for pin
water_cell_111 = openmc.Cell(fill=waterLF1)
#Water Pin
water111_universe = openmc.Universe(cells=(water_cell_111,))
lat_211 = openmc.HexLattice(name="Lower Fissile Zone 1", lattice_id=211)
lat_211.center = (0., 0.)
lat_211.pitch = [0.941]
lat_211.outer = water111_universe
ring1 = [pin11_universe]*6*11
ring2 = [pin11_universe]*6*10
ring3 = [pin11_universe]*6*9
ring4 = [pin11_universe]*6*8
ring5 = [pin11_universe]*6*7
ring6 = [pin11_universe]*6*6
ring7 = [pin11_universe]*6*5
ring8 = [pin11_universe]*6*4
ring9 = [pin11_universe]*6*3
ring10 = [pin11_universe]*6*2
ring11 = [pin11_universe]*6
ring12 = [pin11_universe]*1
lat_211.universes = [ring1,ring2,ring3,ring4,ring5,ring6,ring7,ring8,ring9,ring10,ring11,ring12]
core_surf_38 = openmc.Plane(-0.5773502692, 1.0, 0.0, 0.0) # Left Corner Plane
core_surf_39 = openmc.Plane( 0.5773502692, 1.0, 0.0, 0.0) # Right Corner Plane
core_surf_31 = openmc.model.hexagonal_prism(edge_length=9.4790/math.cos(30/180*math.pi),orientation='y') # Inner can
core_surf_32 = openmc.model.hexagonal_prism(edge_length=9.679/math.cos(30/180*math.pi),orientation='y')# Outer can
core_surf_33 = openmc.model.hexagonal_prism(edge_length=9.7428/math.cos(30/180*math.pi),orientation='y') # Large gap, coolant layer 1
core_surf_34 = openmc.model.hexagonal_prism(edge_length=9.7830/math.cos(30/180*math.pi),orientation='y') # Large gap, CR stainless steel sheath
core_surf_35 = openmc.model.hexagonal_prism(edge_length=9.8100/math.cos(30/180*math.pi),orientation='y') # Large gap, coolant layer 2/follower
core_surf_36 = openmc.model.hexagonal_prism(edge_length=9.8390/math.cos(30/180*math.pi),orientation='y') # Large gap, Zr CR cladding/follower
core_surf_37 = openmc.model.hexagonal_prism(edge_length=9.8833/math.cos(30/180*math.pi),orientation='y',boundary_type='reflective') # Large gap, CR absorber/follower,unitcell
watersmallB_region = ~core_surf_32 & -core_surf_38 & +core_surf_39
watersmallA_region = ~core_surf_32 & +core_surf_38
crod_region = ~core_surf_36 & -core_surf_38 & -core_surf_39
crclad_region = ~core_surf_35 & core_surf_36 & -core_surf_38 & -core_surf_39
waterlar_region = ~core_surf_34 & core_surf_35 & -core_surf_38 & -core_surf_39
sheath_region = ~core_surf_33 & core_surf_34 & -core_surf_38 & -core_surf_39
waterlarge_region = ~core_surf_32 & core_surf_33 & -core_surf_38 & -core_surf_39
cani_region = ~core_surf_31 & core_surf_32
assyi_region = core_surf_31
#For UR1
waterlargeUR1_region = ~core_surf_32& -core_surf_38 & -core_surf_39
LFZ1pin1 = openmc.Universe(universe_id=301, name='LFZ1pin1')
assyi = openmc.Cell(fill=lat_211, region= assyi_region)
cani = openmc.Cell(fill=cladb, region= cani_region)
waterlarge = openmc.Cell(fill=waterwideLF1, region= waterlarge_region)
sheath = openmc.Cell(fill=shthc, region= sheath_region)
waterlar = openmc.Cell(fill=follower, region= waterlar_region)
crclad = openmc.Cell(fill=follower, region= crclad_region)
crod = openmc.Cell(fill=follower, region= crod_region)
watersmallA= openmc.Cell(fill=waternarrowLF1, region= watersmallA_region)
watersmallB= openmc.Cell(fill=waternarrowLF1, region= watersmallB_region)
LFZ1pin1.add_cells((assyi,cani,waterlarge,sheath,waterlar,crclad,crod,watersmallA,watersmallB))