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https://github.com/openmc-dev/openmc.git
synced 2026-07-27 13:45:36 -04:00
Revised existing MG tests to use my 1d problem since I had angular xs and tabular scattering kernels already generated; added tests for max_order and nuclidic data instead of macroscopic mgxs data. Fixed a bug related to doing the nuclidic data.
This commit is contained in:
Adam Nelson
parent
bd39cbe59e
commit
d6f71ff603
17 changed files with 12991 additions and 3984 deletions
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@ -4463,6 +4463,13 @@ contains
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else
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listing % zaid = -1
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end if
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if (check_for_node(node_xsdata, "awr")) then
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call get_node_value(node_xsdata, "awr", listing % awr)
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else
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! Set to a default of 1; this allows a macroscopic library to still
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! be used with materials with atom/b-cm units for testing purposes
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listing % awr = ONE
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end if
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if (check_for_node(node_xsdata, "kT")) then
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call get_node_value(node_xsdata, "kT", listing % kT)
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else
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@ -653,18 +653,18 @@ contains
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mat => materials(i_mat)
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! Check to see how our nuclides are represented
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! Assume all are the same type
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! Therefore type(nuclides(1) % obj) dictates type(macroxs)
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! Force all to be the same type
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! Therefore type(nuclides(mat % nuclide(1)) % obj) dictates type(macroxs)
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! At the same time, we will find the scattering type, as that will dictate
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! how we allocate the scatter object within macroxs
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legendre_mu_points = nuclides_MG(1) % obj % legendre_mu_points
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select type(nuc => nuclides_MG(1) % obj)
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legendre_mu_points = nuclides_MG(mat % nuclide(1)) % obj % legendre_mu_points
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select type(nuc => nuclides_MG(mat % nuclide(1)) % obj)
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type is (Nuclide_Iso)
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representation = ISOTROPIC
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type is (Nuclide_Angle)
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representation = ANGLE
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end select
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scatt_type = nuclides_MG(1) % obj % scatt_type
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scatt_type = nuclides_MG(mat % nuclide(1)) % obj % scatt_type
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! Now allocate accordingly
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select case(representation)
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@ -543,8 +543,9 @@ module nuclide_header
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! Basic nuclide information
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write(unit_,*) 'Nuclide ' // trim(this % name)
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if (this % zaid > 0) then
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! Dont print if data was macroscopic and thus zaid would be nonsense
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! Dont print if data was macroscopic and thus zaid & AWR would be nonsense
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write(unit_,*) ' zaid = ' // trim(to_str(this % zaid))
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write(unit_,*) ' awr = ' // trim(to_str(this % awr))
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end if
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write(unit_,*) ' kT = ' // trim(to_str(this % kT))
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if (this % scatt_type == ANGLE_LEGENDRE) then
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9859
tests/1d_mgxs.xml
Normal file
9859
tests/1d_mgxs.xml
Normal file
File diff suppressed because it is too large
Load diff
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@ -1,383 +0,0 @@
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<?xml version="1.0"?>
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<library>
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<!-- Before getting to the data, set common information -->
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<groups> 7 </groups>
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<group_structure>
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1E-11 0.0635E-6 10.0E-6 1.0E-4 1.0E-3 0.5 1.0 20.0
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</group_structure>
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<!--
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Move on to the data. Each <xsdata> has a unique id and label.
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-->
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<xsdata>
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<!-- Meta data for this data -->
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<name>UO2.71c</name>
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<alias>UO2.71c</alias>
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<kT> 2.53E-8 </kT> <!-- in MeV -->
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<order>0</order>
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<fissionable>true</fissionable>
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<!-- Optional (default is isotropic) -->
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<representation>isotropic</representation>
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<!-- The data itself, like tallies,
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goes from low energies (groups) to high energies
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-->
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<absorption>
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8.0248E-03 3.7174E-03 2.6769E-02 9.6236E-02 3.0020E-02 1.1126E-01 2.8278E-01
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</absorption>
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<nu_fission>
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2.005998E-02 2.027303E-03 1.570599E-02 4.518301E-02 4.334208E-02 2.020901E-01 5.257105E-01
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</nu_fission>
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<chi>
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5.8791E-01 4.1176E-01 3.3906E-04 1.1761E-07 0.0000E+00 0.0000E+00 0.0000E+00
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</chi>
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<fission>
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7.21206E-03 8.19301E-04 6.45320E-03 1.85648E-02 1.78084E-02 8.30348E-02 2.16004E-01
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</fission>
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<!-- units of MeV/cm -->
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<!-- If no kappa fission tallies, this is not needed; it will not be loaded
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if there is no kappa fission scores anyways -->
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<k_fission>
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1.0 1.0 1.0 1.0 1.0 1.0 1.0
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</k_fission>
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<!-- for consistency must include nu-scatter -->
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<!-- will be a matrix of (order+1) x g_in x g_out -->
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<scatter>
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0.1275370 0.0423780 0.0000094 0.0000000 0.0000000 0.0000000 0.0000000
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0.0000000 0.3244560 0.0016314 0.0000000 0.0000000 0.0000000 0.0000000
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0.0000000 0.0000000 0.4509400 0.0026792 0.0000000 0.0000000 0.0000000
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0.0000000 0.0000000 0.0000000 0.4525650 0.0055664 0.0000000 0.0000000
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0.0000000 0.0000000 0.0000000 0.0001253 0.2714010 0.0102550 0.0000000
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0.0000000 0.0000000 0.0000000 0.0000000 0.0012968 0.2658020 0.0168090
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0.0000000 0.0000000 0.0000000 0.0000000 0.0000000 0.0085458 0.2730800
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</scatter>
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<!-- If total is not provided, it will be calculated.
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However, in the C5G7 problems, we want to use a transport-corrected value
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so we dont want to have it be calculated -->
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<total>
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0.1779492 0.3298048 0.4803882 0.5543674000000001 0.3118013 0.39516779999999996 0.5644058
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</total>
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</xsdata>
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<xsdata>
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<!-- Meta data for this data -->
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<name>MOX1.71c</name>
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<alias>MOX1.71c</alias>
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<kT> 2.53E-8 </kT> <!-- in MeV -->
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<order>0</order>
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<fissionable>true</fissionable>
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<!-- The data itself, like tallies,
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goes from low energies (groups) to high energies
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-->
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<absorption>
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8.4339E-03 3.7577E-03 2.7970E-02 1.0421E-01 1.3994E-01 4.0918E-01 4.0935E-01
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</absorption>
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<!--
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Since chi_vector is false, this will be a matrix
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Matrix is g_in, g_out.
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This is to show that you can either use a chi vector + nu_fission vector,
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like in the UO2 data, or a nu_fission matrix like here.
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-->
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<nu_fission>
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1.27888062E-02 8.95701528E-03 7.37557218E-06 2.55837033E-09 0.00000000E+00 0.00000000E+00 0.00000000E+00
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1.49041240E-03 1.04385401E-03 8.59552023E-07 2.98153464E-10 0.00000000E+00 0.00000000E+00 0.00000000E+00
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9.56411400E-03 6.69850756E-03 5.51582469E-06 1.91327830E-09 0.00000000E+00 0.00000000E+00 0.00000000E+00
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3.84928781E-02 2.69596154E-02 2.21996483E-05 7.70040890E-09 0.00000000E+00 0.00000000E+00 0.00000000E+00
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1.80629998E-02 1.26509513E-02 1.04173100E-05 3.61346022E-09 0.00000000E+00 0.00000000E+00 0.00000000E+00
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3.91930789E-01 2.74500216E-01 2.26034688E-04 7.84048241E-08 0.00000000E+00 0.00000000E+00 0.00000000E+00
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4.19762096E-01 2.93992687E-01 2.42085585E-04 8.39724109E-08 0.00000000E+00 0.00000000E+00 0.00000000E+00
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</nu_fission>
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<fission>
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7.62704E-03 8.76898E-04 5.69835E-03 2.28872E-02 1.07635E-02 2.32757E-01 2.48968E-01
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</fission>
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<!-- units of MeV/cm -->
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<k_fission>
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1.0 1.0 1.0 1.0 1.0 1.0 1.0
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</k_fission>
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<!-- for consistency must include nu-scatter -->
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<!-- will be a matrix of (order+1) x g_in x g_out -->
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<scatter>
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1.27537000E-01 4.23780000E-02 9.43740000E-06 5.51630000E-09 0.00000000E+00 0.00000000E+00 0.00000000E+00
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0.00000000E+00 3.24456000E-01 1.63140000E-03 3.14270000E-09 0.00000000E+00 0.00000000E+00 0.00000000E+00
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0.00000000E+00 0.00000000E+00 4.50940000E-01 2.67920000E-03 0.00000000E+00 0.00000000E+00 0.00000000E+00
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0.00000000E+00 0.00000000E+00 0.00000000E+00 4.52565000E-01 5.56640000E-03 0.00000000E+00 0.00000000E+00
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0.00000000E+00 0.00000000E+00 0.00000000E+00 1.25250000E-04 2.71401000E-01 1.02550000E-02 1.00210000E-08
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0.00000000E+00 0.00000000E+00 0.00000000E+00 0.00000000E+00 1.29680000E-03 2.65802000E-01 1.68090000E-02
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0.00000000E+00 0.00000000E+00 0.00000000E+00 0.00000000E+00 0.00000000E+00 8.54580000E-03 2.73080000E-01
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</scatter>
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<total>
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0.1783583429163 0.3298451031427 0.4815892 0.5623414 0.421721260021 0.6930878 0.6909757999999999
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</total>
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</xsdata>
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<xsdata>
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<!-- Meta data for this data -->
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<name>MOX2.71c</name>
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<alias>MOX2.71c</alias>
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<kT> 2.53E-8 </kT> <!-- in MeV -->
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<order>0</order>
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<fissionable>true</fissionable>
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<!-- The data itself, like tallies,
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goes from low energies (groups) to high energies
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-->
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<absorption>
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0.0090657 0.0042967 0.032881 0.12203 0.18298 0.56846 0.58521
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</absorption>
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<!--
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Since chi_vector is false, this will be a matrix
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Matrix is g_in, g_out !!! Need to get these values looking right to match
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output of a nu-fission tally with <energy> filter above <energyout> filter
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-->
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<nu_fission>
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1.40004593E-02 9.80563205E-03 8.07435789E-06 2.80075866E-09 0.00000000E+00 0.00000000E+00 0.00000000E+00
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2.26856185E-03 1.58885378E-03 1.30832709E-06 4.53820413E-10 0.00000000E+00 0.00000000E+00 0.00000000E+00
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1.41886199E-02 9.93741584E-03 8.18287404E-06 2.83839974E-09 0.00000000E+00 0.00000000E+00 0.00000000E+00
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5.54788444E-02 3.88562347E-02 3.19958106E-05 1.10984111E-08 0.00000000E+00 0.00000000E+00 0.00000000E+00
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2.69085702E-02 1.88462058E-02 1.55187355E-05 5.38299559E-09 0.00000000E+00 0.00000000E+00 0.00000000E+00
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5.45687127E-01 3.82187973E-01 3.14709185E-04 1.09163414E-07 0.00000000E+00 0.00000000E+00 0.00000000E+00
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6.13307712E-01 4.29548032E-01 3.53707392E-04 1.22690752E-07 0.00000000E+00 0.00000000E+00 0.00000000E+00
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</nu_fission>
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<fission>
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0.00825446 0.00132565 0.00842156 0.032873 0.0159636 0.323794 0.362803
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</fission>
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<!-- units of MeV/cm -->
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<k_fission>
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1.0 1.0 1.0 1.0 1.0 1.0 1.0
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</k_fission>
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<!-- for consistency must include nu-scatter -->
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<!-- will be a matrix of (order+1) x g_in x g_out -->
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<scatter>
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1.30457000E-01 4.17920000E-02 8.51050000E-06 5.13290000E-09 0.00000000E+00 0.00000000E+00 0.00000000E+00
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0.00000000E+00 3.28428000E-01 1.64360000E-03 2.20170000E-09 0.00000000E+00 0.00000000E+00 0.00000000E+00
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0.00000000E+00 0.00000000E+00 4.58371000E-01 2.53310000E-03 0.00000000E+00 0.00000000E+00 0.00000000E+00
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0.00000000E+00 0.00000000E+00 0.00000000E+00 4.63709000E-01 5.47660000E-03 0.00000000E+00 0.00000000E+00
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0.00000000E+00 0.00000000E+00 0.00000000E+00 1.76190000E-04 2.82313000E-01 8.72890000E-03 9.00160000E-09
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0.00000000E+00 0.00000000E+00 0.00000000E+00 0.00000000E+00 2.27600000E-03 2.49751000E-01 1.31140000E-02
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0.00000000E+00 0.00000000E+00 0.00000000E+00 0.00000000E+00 0.00000000E+00 8.86450000E-03 2.59529000E-01
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</scatter>
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<total>
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0.1813232156329 0.3343683022017 0.4937851 0.5912156 0.47419809900160004 0.833601 0.8536035
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</total>
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</xsdata>
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<xsdata>
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<!-- Meta data for this data -->
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<name>MOX3.71c</name>
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<alias>MOX3.71c</alias>
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<kT> 2.53E-8 </kT> <!-- in MeV -->
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<order>0</order>
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<fissionable>true</fissionable>
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|
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<!-- The data itself, like tallies,
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goes from low energies (groups) to high energies
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-->
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<absorption>
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9.48620000E-03 4.65560000E-03 3.62400000E-02 1.32720000E-01 2.08400000E-01 6.58700000E-01 6.90170000E-01
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</absorption>
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<!--
|
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Since chi_vector is false, this will be a matrix
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Matrix is g_in, g_out !!! Need to get these values looking right to match
|
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output of a nu-fission tally with <energy> filter above <energyout> filter
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-->
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<nu_fission>
|
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1.48071013E-02 1.03705874E-02 8.53956516E-06 2.96212546E-09 0.00000000E+00 0.00000000E+00 0.00000000E+00
|
||||
2.78640474E-03 1.95154023E-03 1.60697792E-06 5.57413653E-10 0.00000000E+00 0.00000000E+00 0.00000000E+00
|
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1.73304404E-02 1.21378819E-02 9.99482763E-06 3.46691346E-09 0.00000000E+00 0.00000000E+00 0.00000000E+00
|
||||
6.59928975E-02 4.62200600E-02 3.80594850E-05 1.32017225E-08 0.00000000E+00 0.00000000E+00 0.00000000E+00
|
||||
3.25131926E-02 2.27715674E-02 1.87510386E-05 6.50418701E-09 0.00000000E+00 0.00000000E+00 0.00000000E+00
|
||||
6.32002662E-01 4.42641588E-01 3.64489161E-04 1.26430632E-07 0.00000000E+00 0.00000000E+00 0.00000000E+00
|
||||
7.28595687E-01 5.10293344E-01 4.20196380E-04 1.45753838E-07 0.00000000E+00 0.00000000E+00 0.00000000E+00
|
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</nu_fission>
|
||||
|
||||
<fission>
|
||||
8.67209000E-03 1.62426000E-03 1.02716000E-02 3.90447000E-02 1.92576000E-02 3.74888000E-01 4.30599000E-01
|
||||
</fission>
|
||||
|
||||
<!-- units of MeV/cm -->
|
||||
<k_fission>
|
||||
1.0 1.0 1.0 1.0 1.0 1.0 1.0
|
||||
</k_fission>
|
||||
|
||||
<!-- for consistency must include nu-scatter -->
|
||||
<!-- will be a matrix of (order+1) x g_in x g_out -->
|
||||
<scatter>
|
||||
1.31504000E-01 4.20460000E-02 8.69720000E-06 5.19380000E-09 0.00000000E+00 0.00000000E+00 0.00000000E+00
|
||||
0.00000000E+00 3.30403000E-01 1.64630000E-03 2.60060000E-09 0.00000000E+00 0.00000000E+00 0.00000000E+00
|
||||
0.00000000E+00 0.00000000E+00 4.61792000E-01 2.47490000E-03 0.00000000E+00 0.00000000E+00 0.00000000E+00
|
||||
0.00000000E+00 0.00000000E+00 0.00000000E+00 4.68021000E-01 5.43300000E-03 0.00000000E+00 0.00000000E+00
|
||||
0.00000000E+00 0.00000000E+00 0.00000000E+00 1.85970000E-04 2.85771000E-01 8.39730000E-03 8.92800000E-09
|
||||
0.00000000E+00 0.00000000E+00 0.00000000E+00 0.00000000E+00 2.39160000E-03 2.47614000E-01 1.23220000E-02
|
||||
0.00000000E+00 0.00000000E+00 0.00000000E+00 0.00000000E+00 0.00000000E+00 8.96810000E-03 2.56093000E-01
|
||||
</scatter>
|
||||
|
||||
<total>
|
||||
1.83044902E-01 3.36704903E-01 5.00506900E-01 6.06174000E-01 5.02754279E-01 9.21027600E-01 9.55231100E-01
|
||||
</total>
|
||||
|
||||
</xsdata>
|
||||
|
||||
<xsdata>
|
||||
<!-- Meta data for this data -->
|
||||
<name>FC.71c</name>
|
||||
<alias>FC.71c</alias>
|
||||
<kT> 2.53E-8 </kT> <!-- in MeV -->
|
||||
<order>0</order>
|
||||
<fissionable>true</fissionable>
|
||||
|
||||
<!-- The data itself, like tallies,
|
||||
goes from low energies (groups) to high energies
|
||||
-->
|
||||
<absorption>
|
||||
5.1132E-04 7.5813E-05 3.1643E-04 1.1675E-03 3.3977E-03 9.1886E-03 2.3244E-02
|
||||
</absorption>
|
||||
|
||||
<nu_fission>
|
||||
1.323401E-08 1.434500E-08 1.128599E-06 1.276299E-05 3.538502E-07 1.740099E-06 5.063302E-06
|
||||
</nu_fission>
|
||||
|
||||
<chi>
|
||||
5.8791E-01 4.1176E-01 3.3906E-04 1.1761E-07 0.0000E+00 0.0000E+00 0.0000E+00
|
||||
</chi>
|
||||
|
||||
<fission>
|
||||
4.79002E-09 5.82564E-09 4.63719E-07 5.24406E-06 1.45390E-07 7.14972E-07 2.08041E-06
|
||||
</fission>
|
||||
|
||||
<!-- units of MeV/cm -->
|
||||
<k_fission>
|
||||
1.0 1.0 1.0 1.0 1.0 1.0 1.0
|
||||
</k_fission>
|
||||
|
||||
<!-- for consistency must include nu-scatter -->
|
||||
<!-- will be a matrix of (order+1) x g_in x g_out -->
|
||||
<scatter>
|
||||
6.61659000E-02 5.90700000E-02 2.83340000E-04 1.46220000E-06 2.06420000E-08 0.00000000E00 0.00000000E00
|
||||
0.00000000E00 2.40377000E-01 5.24350000E-02 2.49900000E-04 1.92390000E-05 2.98750000E-06 4.21400000E-07
|
||||
0.00000000E00 0.00000000E00 1.83425000E-01 9.22880000E-02 6.93650000E-03 1.07900000E-03 2.05430000E-04
|
||||
0.00000000E00 0.00000000E00 0.00000000E00 7.90769000E-02 1.69990000E-01 2.58600000E-02 4.92560000E-03
|
||||
0.00000000E00 0.00000000E00 0.00000000E00 3.73400000E-05 9.97570000E-02 2.06790000E-01 2.44780000E-02
|
||||
0.00000000E00 0.00000000E00 0.00000000E00 0.00000000E00 9.17420000E-04 3.16774000E-01 2.38760000E-01
|
||||
0.00000000E00 0.00000000E00 0.00000000E00 0.00000000E00 0.00000000E00 4.97930000E-02 1.09910000E00
|
||||
</scatter>
|
||||
|
||||
<total>
|
||||
1.26032048E-01 2.93160367E-01 2.84250824E-01 2.81025244E-01 3.34460185E-01 5.65640735E-01 1.17213908E00
|
||||
</total>
|
||||
|
||||
</xsdata>
|
||||
|
||||
<xsdata>
|
||||
<!-- Meta data for this data -->
|
||||
<name>GT.71c</name>
|
||||
<alias>GT.71c</alias>
|
||||
<kT> 2.53E-8 </kT> <!-- in MeV -->
|
||||
<order>0</order>
|
||||
<fissionable>false</fissionable>
|
||||
|
||||
<!-- The data itself, like tallies,
|
||||
goes from low energies (groups) to high energies
|
||||
-->
|
||||
<absorption>
|
||||
5.11320000E-04 7.58010000E-05 3.15720000E-04 1.15820000E-03 3.39750000E-03 9.18780000E-03 2.32420000E-02
|
||||
</absorption>
|
||||
|
||||
<!-- for consistency must include nu-scatter -->
|
||||
<!-- will be a matrix of (order+1) x g_in x g_out -->
|
||||
<scatter>
|
||||
6.61659000E-02 5.90700000E-02 2.83340000E-04 1.46220000E-06 2.06420000E-08 0.00000000E+00 0.00000000E+00
|
||||
0.00000000E+00 2.40377000E-01 5.24350000E-02 2.49900000E-04 1.92390000E-05 2.98750000E-06 4.21400000E-07
|
||||
0.00000000E+00 0.00000000E+00 1.83297000E-01 9.23970000E-02 6.94460000E-03 1.08030000E-03 2.05670000E-04
|
||||
0.00000000E+00 0.00000000E+00 0.00000000E+00 7.88511000E-02 1.70140000E-01 2.58810000E-02 4.92970000E-03
|
||||
0.00000000E+00 0.00000000E+00 0.00000000E+00 3.73330000E-05 9.97372000E-02 2.06790000E-01 2.44780000E-02
|
||||
0.00000000E+00 0.00000000E+00 0.00000000E+00 0.00000000E+00 9.17260000E-04 3.16765000E-01 2.38770000E-01
|
||||
0.00000000E+00 0.00000000E+00 0.00000000E+00 0.00000000E+00 0.00000000E+00 4.97920000E-02 1.09912000E+00
|
||||
</scatter>
|
||||
|
||||
<total>
|
||||
1.26032043E-01 2.93160349E-01 2.84240290E-01 2.80960000E-01 3.34440033E-01 5.65640060E-01 1.17215400E+00
|
||||
</total>
|
||||
</xsdata>
|
||||
|
||||
<xsdata>
|
||||
<!-- Meta data for this data -->
|
||||
<name>LWTR.71c</name>
|
||||
<alias>LWTR.71c</alias>
|
||||
<kT> 2.53E-8 </kT> <!-- in MeV -->
|
||||
<order>0</order>
|
||||
<fissionable>false</fissionable>
|
||||
|
||||
<!-- The data itself, like tallies,
|
||||
goes from low energies (groups) to high energies
|
||||
-->
|
||||
<absorption>
|
||||
6.0105E-04 1.5793E-05 3.3716E-04 1.9406E-03 5.7416E-03 1.5001E-02 3.7239E-02
|
||||
</absorption>
|
||||
|
||||
<!-- for consistency must include nu-scatter -->
|
||||
<!-- will be a matrix of (order+1) x g_in x g_out -->
|
||||
<scatter>
|
||||
0.0444777 0.1134000 0.0007235 0.0000037 0.0000001 0.0000000 0.0000000
|
||||
0.0000000 0.2823340 0.1299400 0.0006234 0.0000480 0.0000074 0.0000010
|
||||
0.0000000 0.0000000 0.3452560 0.2245700 0.0169990 0.0026443 0.0005034
|
||||
0.0000000 0.0000000 0.0000000 0.0910284 0.4155100 0.0637320 0.0121390
|
||||
0.0000000 0.0000000 0.0000000 0.0000714 0.1391380 0.5118200 0.0612290
|
||||
0.0000000 0.0000000 0.0000000 0.0000000 0.0022157 0.6999130 0.5373200
|
||||
0.0000000 0.0000000 0.0000000 0.0000000 0.0000000 0.1324400 2.4807000
|
||||
</scatter>
|
||||
|
||||
<total>
|
||||
0.15920605 0.41296959299999997 0.59030986 0.5843499999999999 0.7180000000000001 1.2544497000000001 2.650379
|
||||
</total>
|
||||
|
||||
</xsdata>
|
||||
|
||||
<xsdata>
|
||||
<!-- Meta data for this data -->
|
||||
<name>CR.71c</name>
|
||||
<alias>CR.71c</alias>
|
||||
<kT> 2.53E-8 </kT> <!-- in MeV -->
|
||||
<order>0</order>
|
||||
<fissionable>false</fissionable>
|
||||
|
||||
<!-- The data itself, like tallies,
|
||||
goes from low energies (groups) to high energies
|
||||
-->
|
||||
<absorption>
|
||||
1.70490000E-03 8.36224000E-03 8.37901000E-02 3.97797000E-01 6.98763000E-01 9.29508000E-01 1.17836000E+00
|
||||
</absorption>
|
||||
|
||||
<!-- for consistency must include nu-scatter -->
|
||||
<!-- will be a matrix of (order+1) x g_in x g_out -->
|
||||
<scatter>
|
||||
1.70563000E-01 4.44012000E-02 9.83670000E-05 1.27786000E-07 0.00000000E+00 0.00000000E+00 0.00000000E+00
|
||||
0.00000000E+00 4.71050000E-01 6.85480000E-04 3.91395000E-10 0.00000000E+00 0.00000000E+00 0.00000000E+00
|
||||
0.00000000E+00 0.00000000E+00 8.01859000E-01 7.20132000E-04 0.00000000E+00 0.00000000E+00 0.00000000E+00
|
||||
0.00000000E+00 0.00000000E+00 0.00000000E+00 5.70752000E-01 1.46015000E-03 0.00000000E+00 0.00000000E+00
|
||||
0.00000000E+00 0.00000000E+00 0.00000000E+00 6.55562000E-05 2.07838000E-01 3.81486000E-03 3.69760000E-09
|
||||
0.00000000E+00 0.00000000E+00 0.00000000E+00 0.00000000E+00 1.02427000E-03 2.02465000E-01 4.75290000E-03
|
||||
0.00000000E+00 0.00000000E+00 0.00000000E+00 0.00000000E+00 0.00000000E+00 3.53043000E-03 6.58597000E-01
|
||||
</scatter>
|
||||
|
||||
<total>
|
||||
2.16767595E-01 4.80097720E-01 8.86369232E-01 9.70009150E-01 9.10481420E-01 1.13775017E+00 1.84048743E+00
|
||||
</total>
|
||||
</xsdata>
|
||||
</library>
|
||||
|
|
@ -572,135 +572,60 @@ class InputSet(object):
|
|||
|
||||
class MGInputSet(InputSet):
|
||||
def build_default_materials_and_geometry(self):
|
||||
# Define materials needed for C5G7 2-D UO2 Assembly
|
||||
uo2_data = openmc.Macroscopic('UO2', '71c')
|
||||
# Define materials needed for 1D/1G slab problem
|
||||
uo2_data = openmc.Macroscopic('uo2_iso', '71c')
|
||||
uo2 = openmc.Material(name='UO2', material_id=1)
|
||||
uo2.set_density('macro', 1.0)
|
||||
uo2.add_macroscopic(uo2_data)
|
||||
|
||||
fiss_cham_data = openmc.Macroscopic('FC', '71c')
|
||||
fiss_cham = openmc.Material(name='FC', material_id=2)
|
||||
fiss_cham.set_density('macro', 1.0)
|
||||
fiss_cham.add_macroscopic(fiss_cham_data)
|
||||
clad_data = openmc.Macroscopic('clad_ang_mu', '71c')
|
||||
clad = openmc.Material(name='Clad', material_id=2)
|
||||
clad.set_density('macro', 1.0)
|
||||
clad.add_macroscopic(clad_data)
|
||||
|
||||
guide_tube_data = openmc.Macroscopic('GT', '71c')
|
||||
guide_tube = openmc.Material(name='GT', material_id=3)
|
||||
guide_tube.set_density('macro', 1.0)
|
||||
guide_tube.add_macroscopic(guide_tube_data)
|
||||
|
||||
water_data = openmc.Macroscopic('LWTR', '71c')
|
||||
water = openmc.Material(name='LWTR', material_id=4)
|
||||
water_data = openmc.Macroscopic('lwtr_iso_mu', '71c')
|
||||
water = openmc.Material(name='LWTR', material_id=3)
|
||||
water.set_density('macro', 1.0)
|
||||
water.add_macroscopic(water_data)
|
||||
|
||||
# Define the materials file.
|
||||
self.materials.default_xs = '71c'
|
||||
self.materials.add_materials((uo2, fiss_cham, guide_tube, water))
|
||||
self.materials.add_materials((uo2, clad, water))
|
||||
|
||||
# Define surfaces.
|
||||
|
||||
# Pin cell
|
||||
s1 = openmc.ZCylinder(R=0.54, surface_id=1)
|
||||
# Assembly/Problem Boundary
|
||||
left = openmc.XPlane(x0=0.0, surface_id=20,
|
||||
left = openmc.XPlane(x0=0.0, surface_id=200,
|
||||
boundary_type='reflective')
|
||||
right = openmc.XPlane(x0=21.42, surface_id=21,
|
||||
right = openmc.XPlane(x0=10.0, surface_id=201,
|
||||
boundary_type='reflective')
|
||||
bottom = openmc.YPlane(y0=0.0, surface_id=22,
|
||||
bottom = openmc.YPlane(y0=0.0, surface_id=300,
|
||||
boundary_type='reflective')
|
||||
top = openmc.YPlane(y0=21.42, surface_id=23,
|
||||
boundary_type='reflective')
|
||||
down = openmc.ZPlane(z0=0.0, surface_id=24,
|
||||
boundary_type='reflective')
|
||||
up = openmc.ZPlane(z0=21.42, surface_id=25,
|
||||
top = openmc.YPlane(y0=10.0, surface_id=301,
|
||||
boundary_type='reflective')
|
||||
|
||||
# Define pin cells
|
||||
# uo2 pin
|
||||
c10 = openmc.Cell(cell_id=10)
|
||||
c10.region = -s1
|
||||
c10.fill = uo2
|
||||
c11 = openmc.Cell(cell_id=11)
|
||||
c11.region = +s1
|
||||
c11.fill = water
|
||||
fuel_pin = openmc.Universe(name='Fuel pin', universe_id=1)
|
||||
fuel_pin.add_cells((c10, c11))
|
||||
down = openmc.ZPlane(z0=0.0, surface_id=0,
|
||||
boundary_type='reflective')
|
||||
fuel_clad_intfc = openmc.ZPlane(z0=2.0, surface_id=1)
|
||||
clad_lwtr_intfc = openmc.ZPlane(z0=2.4, surface_id=2)
|
||||
up = openmc.ZPlane(z0=5.0, surface_id=3,
|
||||
boundary_type='reflective')
|
||||
|
||||
# Fission chamber pin
|
||||
c20 = openmc.Cell(cell_id=20)
|
||||
c20.region = -s1
|
||||
c20.fill = fiss_cham
|
||||
c21 = openmc.Cell(cell_id=21)
|
||||
c21.region = +s1
|
||||
c21.fill = water
|
||||
fiss_chamber_pin = openmc.Universe(name='Fission Chamber', universe_id=2)
|
||||
fiss_chamber_pin.add_cells((c20, c21))
|
||||
|
||||
# Guide Tube pin
|
||||
c30 = openmc.Cell(cell_id=30)
|
||||
c30.region = -s1
|
||||
c30.fill = guide_tube
|
||||
c31 = openmc.Cell(cell_id=31)
|
||||
c31.region = +s1
|
||||
c31.fill = water
|
||||
gt_pin = openmc.Universe(name='Guide Tube', universe_id=3)
|
||||
gt_pin.add_cells((c30, c31))
|
||||
|
||||
# Define fuel lattice
|
||||
l100 = openmc.RectLattice(name='UO2 assembly', lattice_id=100)
|
||||
l100.dimension = (17, 17)
|
||||
l100.lower_left = (-10.71, -10.71)
|
||||
l100.pitch = (1.26, 1.26)
|
||||
l100.universes = [
|
||||
[fuel_pin]*17,
|
||||
[fuel_pin]*17,
|
||||
[fuel_pin]*5 + [gt_pin] + [fuel_pin]*2 + [gt_pin]
|
||||
+ [fuel_pin]*2 + [gt_pin] + [fuel_pin]*5,
|
||||
[fuel_pin]*3 + [gt_pin] + [fuel_pin]*9 + [gt_pin]
|
||||
+ [fuel_pin]*3,
|
||||
[fuel_pin]*17,
|
||||
[fuel_pin]*2 + [gt_pin] + [fuel_pin]*2 + [gt_pin]
|
||||
+ [fuel_pin]*2 + [gt_pin] + [fuel_pin]*2 + [gt_pin]
|
||||
+ [fuel_pin]*2 + [gt_pin] + [fuel_pin]*2,
|
||||
[fuel_pin]*17,
|
||||
[fuel_pin]*17,
|
||||
[fuel_pin]*2 + [gt_pin] + [fuel_pin]*2 + [gt_pin]
|
||||
+ [fuel_pin]*2 + [fiss_chamber_pin] + [fuel_pin]*2 + [gt_pin]
|
||||
+ [fuel_pin]*2 + [gt_pin] + [fuel_pin]*2,
|
||||
[fuel_pin]*17,
|
||||
[fuel_pin]*17,
|
||||
[fuel_pin]*2 + [gt_pin] + [fuel_pin]*2 + [gt_pin]
|
||||
+ [fuel_pin]*2 + [gt_pin] + [fuel_pin]*2 + [gt_pin]
|
||||
+ [fuel_pin]*2 + [gt_pin] + [fuel_pin]*2,
|
||||
[fuel_pin]*17,
|
||||
[fuel_pin]*3 + [gt_pin] + [fuel_pin]*9 + [gt_pin]
|
||||
+ [fuel_pin]*3,
|
||||
[fuel_pin]*5 + [gt_pin] + [fuel_pin]*2 + [gt_pin]
|
||||
+ [fuel_pin]*2 + [gt_pin] + [fuel_pin]*5,
|
||||
[fuel_pin]*17,
|
||||
[fuel_pin]*17 ]
|
||||
|
||||
# Define assemblies.
|
||||
fa = openmc.Universe(name='Fuel assembly', universe_id=10)
|
||||
c100 = openmc.Cell(cell_id=110)
|
||||
c100.region = +down & -up
|
||||
c100.fill = l100
|
||||
fa.add_cells((c100, ))
|
||||
|
||||
# Define core lattices
|
||||
l200 = openmc.RectLattice(name='Core lattice', lattice_id=200)
|
||||
l200.dimension = (1, 1)
|
||||
l200.lower_left = (0.0, 0.0)
|
||||
l200.pitch = (21.42, 21.42)
|
||||
l200.universes = [[fa]]
|
||||
# Define cells
|
||||
c1 = openmc.Cell(cell_id=1)
|
||||
c1.region = +left & -right & +bottom & -top & +down & -fuel_clad_intfc
|
||||
c1.fill = uo2
|
||||
c2 = openmc.Cell(cell_id=2)
|
||||
c2.region = +left & -right & +bottom & -top & +fuel_clad_intfc & -clad_lwtr_intfc
|
||||
c2.fill = clad
|
||||
c3 = openmc.Cell(cell_id=3)
|
||||
c3.region = +left & -right & +bottom & -top & +clad_lwtr_intfc & -up
|
||||
c3.fill = water
|
||||
|
||||
# Define root universe.
|
||||
root = openmc.Universe(universe_id=0, name='root universe')
|
||||
c1 = openmc.Cell(cell_id=1)
|
||||
c1.region = +left & -right & +bottom & -top & +down & -up
|
||||
c1.fill = l200
|
||||
|
||||
root.add_cells((c1,))
|
||||
root.add_cells((c1,c2,c3))
|
||||
|
||||
# Define the geometry file.
|
||||
geometry = openmc.Geometry()
|
||||
|
|
@ -713,15 +638,16 @@ class MGInputSet(InputSet):
|
|||
self.settings.batches = 10
|
||||
self.settings.inactive = 5
|
||||
self.settings.particles = 100
|
||||
self.settings.set_source_space('box', (0.0, 0.0, 0.0, 21.42, 21.42, 100.0))
|
||||
self.settings.set_source_space('box', (0.0, 0.0, 0.0, 10.0, 10.0, 2.0))
|
||||
self.settings.energy_mode = "multi-group"
|
||||
self.settings.cross_sections = "../c5g7_mgxs.xml"
|
||||
self.settings.cross_sections = "../1d_mgxs.xml"
|
||||
|
||||
def build_defualt_plots(self):
|
||||
plot = openmc.Plot()
|
||||
plot.filename = 'mat'
|
||||
plot.origin = (10.71, 10.71, 50.0)
|
||||
plot.width = (21.42, 21.42)
|
||||
plot.origin = (5.0, 5.0, 2.5)
|
||||
plot.width = (2.5, 2.5)
|
||||
plot.basis = 'xz'
|
||||
plot.pixels = (3000, 3000)
|
||||
plot.color = 'mat'
|
||||
|
||||
|
|
|
|||
|
|
@ -1 +1 @@
|
|||
b41c9621e2f068dab8f44b4fbf29aa5f075c04e463543550b7d1324b75b4709db810808e64474d2400c8c36465814bcca095650b0e19d640860dd4a860bb40a3
|
||||
be47096ff6382e07c58c67870eb1c77402c961ee8cb9a4671b52627f6432fe282403e70f5825c90764758fcabe5a480653a961e24d7a0349929283848e79667d
|
||||
|
|
@ -1,2 +1,2 @@
|
|||
k-combined:
|
||||
1.359283E+00 7.465863E-02
|
||||
1.035488E+00 4.058903E-02
|
||||
|
|
|
|||
1
tests/test_mg_max_order/inputs_true.dat
Normal file
1
tests/test_mg_max_order/inputs_true.dat
Normal file
|
|
@ -0,0 +1 @@
|
|||
7bd8b00b5aaad3913e0022269cf6ef92dfd0051bd79fb136838ea5a65d322d9711b454e62ef03dcf2b9dd75e31a4febcc633f968d7d07dcb6da2e0d36daf45db
|
||||
2
tests/test_mg_max_order/results_true.dat
Normal file
2
tests/test_mg_max_order/results_true.dat
Normal file
|
|
@ -0,0 +1,2 @@
|
|||
k-combined:
|
||||
1.106635E+00 4.503267E-02
|
||||
85
tests/test_mg_max_order/test_mg_max_order.py
Normal file
85
tests/test_mg_max_order/test_mg_max_order.py
Normal file
|
|
@ -0,0 +1,85 @@
|
|||
#!/usr/bin/env python
|
||||
|
||||
import os
|
||||
import sys
|
||||
sys.path.insert(0, os.pardir)
|
||||
from testing_harness import TestHarness, PyAPITestHarness
|
||||
from input_set import MGInputSet
|
||||
import openmc
|
||||
|
||||
class MGNuclideInputSet(MGInputSet):
|
||||
def build_default_materials_and_geometry(self):
|
||||
# Define materials needed for 1D/1G slab problem
|
||||
uo2_data = openmc.Macroscopic('uo2_iso', '71c')
|
||||
uo2 = openmc.Material(name='UO2', material_id=1)
|
||||
uo2.set_density('macro', 1.0)
|
||||
uo2.add_macroscopic(uo2_data)
|
||||
|
||||
clad_data = openmc.Macroscopic('clad_iso', '71c')
|
||||
clad = openmc.Material(name='Clad', material_id=2)
|
||||
clad.set_density('macro', 1.0)
|
||||
clad.add_macroscopic(clad_data)
|
||||
|
||||
water_data = openmc.Macroscopic('lwtr_iso', '71c')
|
||||
water = openmc.Material(name='LWTR', material_id=3)
|
||||
water.set_density('macro', 1.0)
|
||||
water.add_macroscopic(water_data)
|
||||
|
||||
# Define the materials file.
|
||||
self.materials.default_xs = '71c'
|
||||
self.materials.add_materials((uo2, clad, water))
|
||||
|
||||
# Define surfaces.
|
||||
|
||||
# Assembly/Problem Boundary
|
||||
left = openmc.XPlane(x0=0.0, surface_id=200,
|
||||
boundary_type='reflective')
|
||||
right = openmc.XPlane(x0=10.0, surface_id=201,
|
||||
boundary_type='reflective')
|
||||
bottom = openmc.YPlane(y0=0.0, surface_id=300,
|
||||
boundary_type='reflective')
|
||||
top = openmc.YPlane(y0=10.0, surface_id=301,
|
||||
boundary_type='reflective')
|
||||
|
||||
down = openmc.ZPlane(z0=0.0, surface_id=0,
|
||||
boundary_type='reflective')
|
||||
fuel_clad_intfc = openmc.ZPlane(z0=2.0, surface_id=1)
|
||||
clad_lwtr_intfc = openmc.ZPlane(z0=2.4, surface_id=2)
|
||||
up = openmc.ZPlane(z0=5.0, surface_id=3,
|
||||
boundary_type='reflective')
|
||||
|
||||
# Define cells
|
||||
c1 = openmc.Cell(cell_id=1)
|
||||
c1.region = +left & -right & +bottom & -top & +down & -fuel_clad_intfc
|
||||
c1.fill = uo2
|
||||
c2 = openmc.Cell(cell_id=2)
|
||||
c2.region = +left & -right & +bottom & -top & +fuel_clad_intfc & -clad_lwtr_intfc
|
||||
c2.fill = clad
|
||||
c3 = openmc.Cell(cell_id=3)
|
||||
c3.region = +left & -right & +bottom & -top & +clad_lwtr_intfc & -up
|
||||
c3.fill = water
|
||||
|
||||
# Define root universe.
|
||||
root = openmc.Universe(universe_id=0, name='root universe')
|
||||
|
||||
root.add_cells((c1,c2,c3))
|
||||
|
||||
# Define the geometry file.
|
||||
geometry = openmc.Geometry()
|
||||
geometry.root_universe = root
|
||||
|
||||
self.geometry.geometry = geometry
|
||||
|
||||
class MGNuclideTestHarness(PyAPITestHarness):
|
||||
def __init__(self, statepoint_name, tallies_present, mg=False):
|
||||
TestHarness.__init__(self, statepoint_name, tallies_present)
|
||||
self._input_set = MGNuclideInputSet()
|
||||
|
||||
def _build_inputs(self):
|
||||
super(MGNuclideTestHarness, self)._build_inputs()
|
||||
# Set P1 scattering
|
||||
self._input_set.settings.max_order = 1
|
||||
|
||||
if __name__ == '__main__':
|
||||
harness = MGNuclideTestHarness('statepoint.10.*', False, mg=True)
|
||||
harness.main()
|
||||
1
tests/test_mg_nuclide/inputs_true.dat
Normal file
1
tests/test_mg_nuclide/inputs_true.dat
Normal file
|
|
@ -0,0 +1 @@
|
|||
f3d614294177f34186bf0d439330d144438ac6a2402af9b5433efb7bf6a311043140c487c86f4d3cae9d51742f5042823d224c9da6365da6c8972b44edb7fb71
|
||||
2
tests/test_mg_nuclide/results_true.dat
Normal file
2
tests/test_mg_nuclide/results_true.dat
Normal file
|
|
@ -0,0 +1,2 @@
|
|||
k-combined:
|
||||
1.271009E-01 6.377851E-03
|
||||
84
tests/test_mg_nuclide/test_mg_nuclide.py
Normal file
84
tests/test_mg_nuclide/test_mg_nuclide.py
Normal file
|
|
@ -0,0 +1,84 @@
|
|||
#!/usr/bin/env python
|
||||
|
||||
import os
|
||||
import sys
|
||||
sys.path.insert(0, os.pardir)
|
||||
from testing_harness import TestHarness, PyAPITestHarness
|
||||
from input_set import MGInputSet
|
||||
import openmc
|
||||
|
||||
class MGNuclideInputSet(MGInputSet):
|
||||
def build_default_materials_and_geometry(self):
|
||||
# Define materials needed for 1D/1G slab problem
|
||||
# This time do using nuclide, not macroscopic
|
||||
uo2 = openmc.Material(name='UO2', material_id=1)
|
||||
uo2.set_density('g/cm3', 1.0)
|
||||
uo2.add_nuclide("uo2_iso", 1.0)
|
||||
|
||||
clad = openmc.Material(name='Clad', material_id=2)
|
||||
clad.set_density('g/cm3', 1.0)
|
||||
clad.add_nuclide("clad_ang_mu", 1.0)
|
||||
|
||||
water_data = openmc.Nuclide('lwtr_iso_mu', '71c')
|
||||
water = openmc.Material(name='LWTR', material_id=3)
|
||||
water.set_density('g/cm3', 1.0)
|
||||
water.add_nuclide("lwtr_iso_mu", 1.0)
|
||||
|
||||
# Define the materials file.
|
||||
self.materials.default_xs = '71c'
|
||||
self.materials.add_materials((uo2, clad, water))
|
||||
|
||||
# Define surfaces.
|
||||
|
||||
# Assembly/Problem Boundary
|
||||
left = openmc.XPlane(x0=0.0, surface_id=200,
|
||||
boundary_type='reflective')
|
||||
right = openmc.XPlane(x0=10.0, surface_id=201,
|
||||
boundary_type='reflective')
|
||||
bottom = openmc.YPlane(y0=0.0, surface_id=300,
|
||||
boundary_type='reflective')
|
||||
top = openmc.YPlane(y0=10.0, surface_id=301,
|
||||
boundary_type='reflective')
|
||||
|
||||
down = openmc.ZPlane(z0=0.0, surface_id=0,
|
||||
boundary_type='reflective')
|
||||
fuel_clad_intfc = openmc.ZPlane(z0=2.0, surface_id=1)
|
||||
clad_lwtr_intfc = openmc.ZPlane(z0=2.4, surface_id=2)
|
||||
up = openmc.ZPlane(z0=5.0, surface_id=3,
|
||||
boundary_type='reflective')
|
||||
|
||||
# Define cells
|
||||
c1 = openmc.Cell(cell_id=1)
|
||||
c1.region = +left & -right & +bottom & -top & +down & -fuel_clad_intfc
|
||||
c1.fill = uo2
|
||||
c2 = openmc.Cell(cell_id=2)
|
||||
c2.region = +left & -right & +bottom & -top & +fuel_clad_intfc & -clad_lwtr_intfc
|
||||
c2.fill = clad
|
||||
c3 = openmc.Cell(cell_id=3)
|
||||
c3.region = +left & -right & +bottom & -top & +clad_lwtr_intfc & -up
|
||||
c3.fill = water
|
||||
|
||||
# Define root universe.
|
||||
root = openmc.Universe(universe_id=0, name='root universe')
|
||||
|
||||
root.add_cells((c1,c2,c3))
|
||||
|
||||
# Define the geometry file.
|
||||
geometry = openmc.Geometry()
|
||||
geometry.root_universe = root
|
||||
|
||||
self.geometry.geometry = geometry
|
||||
|
||||
class MGNuclideTestHarness(PyAPITestHarness):
|
||||
def __init__(self, statepoint_name, tallies_present, mg=False):
|
||||
TestHarness.__init__(self, statepoint_name, tallies_present)
|
||||
self._input_set = MGNuclideInputSet()
|
||||
|
||||
def _build_inputs(self):
|
||||
super(MGNuclideTestHarness, self)._build_inputs()
|
||||
|
||||
|
||||
|
||||
if __name__ == '__main__':
|
||||
harness = MGNuclideTestHarness('statepoint.10.*', False, mg=True)
|
||||
harness.main()
|
||||
|
|
@ -1 +1 @@
|
|||
87d5adff4c8d53f020baa25db59d9ad6eada791ef010577e3586c543a9ee6cee6022d99e7a27911a94560acddba3602570c0748a0b4cba48f630b726221f14dc
|
||||
dcde495bd5d0ace409154be3529ae91d454e92f7060e38f00bc0880350d53c889b87edcfd481e6c8bcec2450bdf780e6fdc52240978eb1c67a6ef290ad85442d
|
||||
File diff suppressed because it is too large
Load diff
|
|
@ -18,11 +18,9 @@ class MGTalliesTestHarness(PyAPITestHarness):
|
|||
|
||||
# Instantiate some tally filters
|
||||
energy_filter = openmc.Filter(type='energy',
|
||||
bins=[1E-11, 0.0635E-6, 10.0E-6, 1.0E-4,
|
||||
1.0E-3, 0.5, 1.0, 20.0])
|
||||
bins=[0.0, 20.0])
|
||||
energyout_filter = openmc.Filter(type='energyout',
|
||||
bins=[1E-11, 0.0635E-6, 10.0E-6,
|
||||
1.0E-4, 1.0E-3, 0.5, 1.0, 20.0])
|
||||
bins=[0.0, 20.0])
|
||||
mesh_filter = openmc.Filter()
|
||||
mesh_filter.mesh = mesh
|
||||
|
||||
|
|
|
|||
Loading…
Add table
Add a link
Reference in a new issue