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fix divergent openmc and serpent model
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yardasol committed Oct 5, 2022
1 parent 3ede9a2 commit 7cec6fb
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Showing 3 changed files with 6 additions and 6 deletions.
2 changes: 1 addition & 1 deletion examples/msbr/mats/msbr_saltproc_prepr_comp_endfb71.ini
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@@ -1,6 +1,6 @@
% Material compositions (after 0.000000 days)

mat fuel -3.350000000E+00 burn 1 fix 09c 900 vol 4.87100E+07
mat fuel -3.350000000E+00 burn 1 fix 82c 900 vol 4.87100E+07
1001.82c -0.00000000000000E+00
1002.82c -0.00000000000000E+00
1003.82c -0.00000000000000E+00
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2 changes: 1 addition & 1 deletion examples/msbr/msbr_endfb71.serpent
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Expand Up @@ -45,7 +45,7 @@ rgb 127 205 187
% --- Thermal scattering data for graphite:
% endfb71
%therm gr 900 grph.25t grph.26t % 900K C-nat
$% endfb70
% endfb70
therm gr 900 grph.15t grph.16t % 900K C-nat


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8 changes: 4 additions & 4 deletions examples/msbr/openmc_model.py
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Expand Up @@ -7,7 +7,7 @@

# Materials

fuel = openmc.Material(name='fuel', temperature=900.0)
fuel = openmc.Material(name='fuel')
fuel.set_density('g/cm3', density=3.35)
fuel.add_components({'Li7': 0.0787474673879085,
'Be9': 0.0225566879138321,
Expand All @@ -18,12 +18,12 @@
fuel.depletable = True
fuel.volume = 48710000.0

moder = openmc.Material(name='graphite', temperature=900.0)
moder = openmc.Material(name='graphite')
moder.set_density('g/cm3', density=1.84)
moder.add_nuclide('C0', 1.000, percent_type='wo')
moder.add_s_alpha_beta('c_Graphite')

hast = openmc.Material(name='hastelloyN', temperature=900.0)
hast = openmc.Material(name='hastelloyN')
hast.set_density('g/cm3', density=8.671)
hast.add_components({'Al27': 0.003,
'Ni': 0.677,
Expand Down Expand Up @@ -153,7 +153,7 @@ def main_lattice(zone_i_boundary, cr_boundary, core_base, core_top):
settings = openmc.Settings()
settings.particles = 300
settings.batches = 400
settings.inative = 5
settings.inactive = 10
settings.temperature = {'default': 900, 'method': 'interpolation'}
settings.export_to_xml()

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