Commit 149f0134 authored by Patrick Shriwise's avatar Patrick Shriwise
Browse files

Some small tweaks to remove warnings in the OpenMC model.

parent 2791e049
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......@@ -108,6 +108,8 @@ temperature_outlet = 273.15 + 700.0 # UCBTH-14-002, Table 1-1
temperature_flibe = (temperature_inlet+temperature_outlet)/2
# --------------------------------------------------
# NO PARAMETERS DEFINITION BEYOND THIS LINE
# -------------- Materials Definition --------------
# TRISO particle
# Fuel from Nagley et al. Fabrication of Uranium Oxycarbide Kernels for HTR Fuel https://inldigitallibrary.inl.gov/sites/sti/sti/4886646.pdf Table 2
......@@ -118,6 +120,7 @@ m_fuel.add_nuclide('U238', 89.58*(1-enrichment_uranium) , percen
m_fuel.add_nuclide('C0' , 1.80 , percent_type='wo')
m_fuel.add_element('O' , 8.62 , percent_type='wo')
m_fuel.set_density(*density_fuel)
#
m_graphite_c_buffer = openmc.Material(name='m_graphite_c_buffer - triso partciles')
m_graphite_c_buffer.set_density(*density_c_buffer)
......@@ -159,13 +162,14 @@ m_flibe.add_element('Be' , 1.0)
m_flibe.add_element('F' , 4.0)
# TODO: FLiBe coolant - no S(alpha, beta) data available up to ENDF/B-VIIIb4
# -------------- Geometry Definition --------------
# TRISO particle universe
s_fuel = openmc.Sphere(R=radius_fuel)
s_c_buffer = openmc.Sphere(R=radius_c_buffer)
s_pyc_inner = openmc.Sphere(R=radius_pyc_inner)
s_sic = openmc.Sphere(R=radius_sic)
s_pyc_outer = openmc.Sphere(R=radius_pyc_outer)
s_fuel = openmc.Sphere(r=radius_fuel)
s_c_buffer = openmc.Sphere(r=radius_c_buffer)
s_pyc_inner = openmc.Sphere(r=radius_pyc_inner)
s_sic = openmc.Sphere(r=radius_sic)
s_pyc_outer = openmc.Sphere(r=radius_pyc_outer)
c_triso_fuel = openmc.Cell(name='TRICO Fuel', fill=m_fuel, region=-s_fuel)
c_triso_c_buffer = openmc.Cell(name='TRISO Graphite Buffer', fill=m_graphite_c_buffer, region=+s_fuel & -s_c_buffer)
c_triso_pyc_inner = openmc.Cell(name='TRISO Pyrolitic Graphite Inner', fill=m_graphite_pyc, region=+s_c_buffer & -s_pyc_inner)
......@@ -177,9 +181,9 @@ triso_cells = [c_triso_fuel, c_triso_c_buffer, c_triso_pyc_inner, c_triso_sic, c
u_triso = openmc.Universe(cells=triso_cells)
# Pebble Geometry
s_pebble_inner = openmc.Sphere(R=radius_pebble_inner)
s_pebble_central = openmc.Sphere(R=radius_pebble_central)
s_pebble_outer = openmc.Sphere(R=radius_pebble_outer)
s_pebble_inner = openmc.Sphere(r=radius_pebble_inner)
s_pebble_central = openmc.Sphere(r=radius_pebble_central)
s_pebble_outer = openmc.Sphere(r=radius_pebble_outer)
c_pebble_inner = openmc.Cell(name='Pebble graphite inner region', fill=m_graphite_inner, region=-s_pebble_inner)
c_pebble_central = openmc.Cell(name='Pebble central region (TRISOs)', region=+s_pebble_inner & -s_pebble_central)
c_pebble_outer = openmc.Cell(name='Pebble graphite outer region', fill=m_graphite_outer, region=+s_pebble_central & -s_pebble_outer)
......@@ -192,7 +196,7 @@ if random_distribution==0:
l_triso.lower_left = (-pitch_triso_lattice/2, -pitch_triso_lattice/2, -pitch_triso_lattice/2)
l_triso.pitch = ( pitch_triso_lattice , pitch_triso_lattice , pitch_triso_lattice)
l_triso.outer = u_triso
l_triso.universes = np.tile(u_triso, (10,10,10))
l_triso.universes = np.tile(u_triso, (20, 20, 20))
# TRISO particles random distribution using 'packing_fraction'
else:
c_triso_pyc_outer_random = openmc.Cell(name='c_triso_pyc_outer_random', fill=m_graphite_pyc, region=+s_sic)
......@@ -222,7 +226,7 @@ pebble_cells = [c_pebble_inner, c_pebble_central, c_pebble_outer, c_pebble_flibe
u_pebble = openmc.Universe(cells=pebble_cells)
# Vessel cell
vessel_barrel = openmc.ZCylinder(x0=vessel_x, y0=vessel_y, R=vessel_radius, boundary_type='reflective')
vessel_barrel = openmc.ZCylinder(x0=vessel_x, y0=vessel_y, r=vessel_radius, boundary_type='reflective')
vessel_bottom = openmc.ZPlane(z0=vessel_z_min, boundary_type='reflective')
vessel_top = openmc.ZPlane(z0=vessel_z_max, boundary_type='reflective')
vessel_region = -vessel_barrel & +vessel_bottom & -vessel_top
......@@ -253,9 +257,9 @@ if verbose:
# -------------- Settings --------------------
settings = openmc.Settings()
settings.source = openmc.Source(space=openmc.stats.Box(*vessel_cell.bounding_box, only_fissionable=True))
settings.particles = 10000
settings.particles = 50000
settings.inactive = 50
settings.batches = 150
settings.batches = 250
settings.temperature = dict(default=573, method='interpolation', multipole=True, range=(300.0, 1500.0), tolerance=1000.0)
# Fuel volume calculation
volume_fuel = openmc.VolumeCalculation([m_fuel], 10000000, *c_pebble_central.bounding_box)
......
<?xml version='1.0' encoding='utf-8'?>
<settings>
<run_mode>eigenvalue</run_mode>
<particles>10000</particles>
<batches>150</batches>
<particles>50000</particles>
<batches>250</batches>
<inactive>50</inactive>
<source strength="1.0">
<space type="fission">
......
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