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Fixed SMR fuel enrichment

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This commit is contained in:
Will Boyd 2017-02-07 20:27:19 -05:00
parent f7d40fc00f
commit 3c5d40662e
5 changed files with 16 additions and 14 deletions
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6
smr/materials.py
View file

@ -192,7 +192,7 @@ mats['UO2 1.6'] = openmc.Material(name='1.6\% Enr. UO2 Fuel')
mats['UO2 1.6'].temperature = 300
mats['UO2 1.6'].set_density('g/cc', 10.31341)
mats['UO2 1.6'].add_element('O', a_O, 'ao')
mats['UO2 1.6'].add_element('U', a_U, 'ao', enrichment=0.0161006)
mats['UO2 1.6'].add_element('U', a_U, 'ao', enrichment=1.61006)
# Create 2.4% enriched UO2 fuel material
a_U234, a_U235, a_U238, a_U, a_O = get_fuel_aos(0.0239993)
@ -200,7 +200,7 @@ mats['UO2 2.4'] = openmc.Material(name='2.4\% Enr. UO2 Fuel')
mats['UO2 2.4'].temperature = 300
mats['UO2 2.4'].set_density('g/cc', 10.29748)
mats['UO2 2.4'].add_element('O', a_O, 'ao')
mats['UO2 2.4'].add_element('U', a_U, 'ao', enrichment=0.0239993)
mats['UO2 2.4'].add_element('U', a_U, 'ao', enrichment=2.39993)
# Create 3.1% enriched UO2 fuel material
a_U234, a_U235, a_U238, a_U, a_O = get_fuel_aos(0.0310221)
@ -208,7 +208,7 @@ mats['UO2 3.1'] = openmc.Material(name='3.1\% Enr. UO2 Fuel')
mats['UO2 3.1'].temperature = 300
mats['UO2 3.1'].set_density('g/cc', 10.30166)
mats['UO2 3.1'].add_element('O', a_O, 'ao')
mats['UO2 3.1'].add_element('U', a_U, 'ao', enrichment=0.0310221)
mats['UO2 3.1'].add_element('U', a_U, 'ao', enrichment=3.10221)
# Construct a collection of Materials to export to XML

18
smr/materials.xml
View file

@ -178,26 +178,26 @@
<density units="g/cc" value="10.31341" />
<nuclide ao="1.9998012531906832" name="O16" />
<nuclide ao="0.0007602133572882293" name="O17" />
<nuclide ao="1.3101134677091015e-06" name="U234" />
<nuclide ao="0.00016306537007819218" name="U235" />
<nuclide ao="0.9998356245164544" name="U238" />
<nuclide ao="0.00013098435147670766" name="U234" />
<nuclide ao="0.016303176995310382" name="U235" />
<nuclide ao="0.9835658386532131" name="U238" />
</material>
<material id="10010" name="2.4\% Enr. UO2 Fuel">
<temperature>300</temperature>
<density units="g/cc" value="10.29748" />
<nuclide ao="1.9998012531906837" name="O16" />
<nuclide ao="0.0007602133572882294" name="O17" />
<nuclide ao="1.9528324431744344e-06" name="U234" />
<nuclide ao="0.00024306241626824177" name="U235" />
<nuclide ao="0.9997549847512887" name="U238" />
<nuclide ao="0.000195223271243839" name="U234" />
<nuclide ao="0.024298776982208982" name="U235" />
<nuclide ao="0.9755059997465472" name="U238" />
</material>
<material id="10011" name="3.1\% Enr. UO2 Fuel">
<temperature>300</temperature>
<density units="g/cc" value="10.30166" />
<nuclide ao="1.9998012531906824" name="O16" />
<nuclide ao="0.0007602133572882289" name="O17" />
<nuclide ao="2.524278138361776e-06" name="U234" />
<nuclide ao="0.00031418831952932034" name="U235" />
<nuclide ao="0.9996832874023323" name="U238" />
<nuclide ao="0.0002523276152188021" name="U234" />
<nuclide ao="0.03140636057161555" name="U235" />
<nuclide ao="0.9683413118131656" name="U238" />
</material>
</materials>

2
smr/plots.py
View file

@ -25,7 +25,7 @@ plots = openmc.Plots()
plot = openmc.Plot(name='radial core map ')
plot.basis = 'xy'
plot.color = 'mat'
plot.origin = [0., 0., 200.] #(highest_extent-lowest_extent)/2.]
plot.origin = [0., 0., (highest_extent-lowest_extent)/2.]
plot.width = [25*lattice_pitch/2, 25*lattice_pitch/2.]
plot.filename = 'radial_core_map'
plot.col_spec = col_spec

2
smr/plots.xml
View file

@ -2,7 +2,7 @@
<plots>
<!--radial core map -->
<plot basis="xy" color="mat" filename="radial_core_map" id="10000" type="slice">
<origin>0.0 0.0 200.0</origin>
<origin>0.0 0.0 127.722</origin>
<width>268.7955 268.7955</width>
<pixels>1000 1000</pixels>
<background>255 255 255</background>

2
smr/settings.xml
View file

@ -14,4 +14,6 @@
<tallies>false</tallies>
</output>
<ptables>true</ptables>
<temperature_multipole>True</temperature_multipole>
<temperature_tolerance>1000</temperature_tolerance>
</settings>