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converted all cross section extensions to 71c for 293.6K NNDC data

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This commit is contained in:
Bryan Herman 2014-04-08 11:28:33 -04:00
parent 3ad1bd2f20
commit b275fcac9d
75 changed files with 135 additions and 135 deletions
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2
tests/test_basic/materials.xml
View file

@ -3,7 +3,7 @@
<material id="1">
<density value="4.5" units="g/cc" />
<nuclide name="U-235" xs="70c" ao="1.0" />
<nuclide name="U-235" xs="71c" ao="1.0" />
</material>
</materials>

6
tests/test_cmfd_feed/materials.xml
View file

@ -4,9 +4,9 @@
<!-- Definition of materials -->
<material id="1">
<density value="19" units="g/cc" />
<nuclide name="U-235" xs="70c" wo="0.21" />
<nuclide name="U-238" xs="70c" wo="0.68" />
<nuclide name="O-16" xs="70c" wo="0.11" />
<nuclide name="U-235" xs="71c" wo="0.21" />
<nuclide name="U-238" xs="71c" wo="0.68" />
<nuclide name="O-16" xs="71c" wo="0.11" />
</material>
</materials>

6
tests/test_cmfd_jfnk/materials.xml
View file

@ -4,9 +4,9 @@
<!-- Definition of materials -->
<material id="1">
<density value="19" units="g/cc" />
<nuclide name="U-235" xs="70c" wo="0.21" />
<nuclide name="U-238" xs="70c" wo="0.68" />
<nuclide name="O-16" xs="70c" wo="0.11" />
<nuclide name="U-235" xs="71c" wo="0.21" />
<nuclide name="U-238" xs="71c" wo="0.68" />
<nuclide name="O-16" xs="71c" wo="0.11" />
</material>
</materials>

6
tests/test_cmfd_nofeed/materials.xml
View file

@ -4,9 +4,9 @@
<!-- Definition of materials -->
<material id="1">
<density value="19" units="g/cc" />
<nuclide name="U-235" xs="70c" wo="0.21" />
<nuclide name="U-238" xs="70c" wo="0.68" />
<nuclide name="O-16" xs="70c" wo="0.11" />
<nuclide name="U-235" xs="71c" wo="0.21" />
<nuclide name="U-238" xs="71c" wo="0.68" />
<nuclide name="O-16" xs="71c" wo="0.11" />
</material>
</materials>

2
tests/test_confidence_intervals/materials.xml
View file

@ -3,7 +3,7 @@
<material id="1">
<density value="4.5" units="g/cc" />
<nuclide name="U-235" xs="70c" ao="1.0" />
<nuclide name="U-235" xs="71c" ao="1.0" />
</material>
</materials>

2
tests/test_density_atombcm/materials.xml
View file

@ -3,7 +3,7 @@
<material id="1">
<density value="0.1" units="atom/b-cm" />
<nuclide name="U-235" xs="70c" ao="1.0" />
<nuclide name="U-235" xs="71c" ao="1.0" />
</material>
</materials>

2
tests/test_density_atomcm3/materials.xml
View file

@ -3,7 +3,7 @@
<material id="1">
<density value="4.5e22" units="atom/cm3" />
<nuclide name="U-235" xs="70c" ao="1.0" />
<nuclide name="U-235" xs="71c" ao="1.0" />
</material>
</materials>

2
tests/test_density_kgm3/materials.xml
View file

@ -3,7 +3,7 @@
<material id="1">
<density value="12.3e3" units="kg/m3" />
<nuclide name="U-235" xs="70c" ao="1.0" />
<nuclide name="U-235" xs="71c" ao="1.0" />
</material>
</materials>

6
tests/test_density_sum/materials.xml
View file

@ -3,9 +3,9 @@
<material id="1">
<density units="sum" />
<nuclide name="U-235" xs="70c" ao="0.3e-2" />
<nuclide name="U-238" xs="70c" ao="0.5e-1" />
<nuclide name="H-1" xs="70c" ao="0.1e-2" />
<nuclide name="U-235" xs="71c" ao="0.3e-2" />
<nuclide name="U-238" xs="71c" ao="0.5e-1" />
<nuclide name="H-1" xs="71c" ao="0.1e-2" />
</material>
</materials>

2
tests/test_eigenvalue_genperbatch/materials.xml
View file

@ -3,7 +3,7 @@
<material id="1">
<density value="4.5" units="g/cc" />
<nuclide name="U-235" xs="70c" ao="1.0" />
<nuclide name="U-235" xs="71c" ao="1.0" />
</material>
</materials>

2
tests/test_eigenvalue_no_inactive/materials.xml
View file

@ -3,7 +3,7 @@
<material id="1">
<density value="4.5" units="g/cc" />
<nuclide name="U-235" xs="70c" ao="1.0" />
<nuclide name="U-235" xs="71c" ao="1.0" />
</material>
</materials>

6
tests/test_energy_grid/materials.xml
View file

@ -3,9 +3,9 @@
<material id="1">
<density value="4.5" units="g/cc" />
<nuclide name="U-235" xs="70c" ao="1.0" />
<nuclide name="H-1" xs="70c" ao="0.5" />
<nuclide name="C-Nat" xs="70c" ao="0.5" />
<nuclide name="U-235" xs="71c" ao="1.0" />
<nuclide name="H-1" xs="71c" ao="0.5" />
<nuclide name="C-Nat" xs="71c" ao="0.5" />
</material>
</materials>

2
tests/test_entropy/materials.xml
View file

@ -3,7 +3,7 @@
<material id="1">
<density value="4.5" units="g/cc" />
<nuclide name="U-235" xs="70c" ao="1.0" />
<nuclide name="U-235" xs="71c" ao="1.0" />
</material>
</materials>

2
tests/test_filter_cell/materials.xml
View file

@ -1,7 +1,7 @@
<?xml version="1.0"?>
<materials>
<default_xs>70c</default_xs>
<default_xs>71c</default_xs>
<!-- Fuel composition -->
<material id="1">

2
tests/test_filter_cellborn/materials.xml
View file

@ -1,7 +1,7 @@
<?xml version="1.0"?>
<materials>
<default_xs>70c</default_xs>
<default_xs>71c</default_xs>
<!-- Fuel composition -->
<material id="1">

2
tests/test_filter_energy/materials.xml
View file

@ -1,7 +1,7 @@
<?xml version="1.0"?>
<materials>
<default_xs>70c</default_xs>
<default_xs>71c</default_xs>
<!-- Fuel composition -->
<material id="1">

2
tests/test_filter_energyout/materials.xml
View file

@ -1,7 +1,7 @@
<?xml version="1.0"?>
<materials>
<default_xs>70c</default_xs>
<default_xs>71c</default_xs>
<!-- Fuel composition -->
<material id="1">

2
tests/test_filter_group_transfer/materials.xml
View file

@ -1,7 +1,7 @@
<?xml version="1.0"?>
<materials>
<default_xs>70c</default_xs>
<default_xs>71c</default_xs>
<!-- Fuel composition -->
<material id="1">

2
tests/test_filter_material/materials.xml
View file

@ -1,7 +1,7 @@
<?xml version="1.0"?>
<materials>
<default_xs>70c</default_xs>
<default_xs>71c</default_xs>
<!-- Fuel composition -->
<material id="1">

2
tests/test_filter_mesh_2d/materials.xml
View file

@ -1,7 +1,7 @@
<?xml version="1.0"?>
<materials>
<default_xs>70c</default_xs>
<default_xs>71c</default_xs>
<!-- Fuel composition -->
<material id="1">

2
tests/test_filter_mesh_3d/materials.xml
View file

@ -1,7 +1,7 @@
<?xml version="1.0"?>
<materials>
<default_xs>70c</default_xs>
<default_xs>71c</default_xs>
<!-- Fuel composition -->
<material id="1">

2
tests/test_filter_universe/materials.xml
View file

@ -1,7 +1,7 @@
<?xml version="1.0"?>
<materials>
<default_xs>70c</default_xs>
<default_xs>71c</default_xs>
<!-- Fuel composition -->
<material id="1">

2
tests/test_fixed_source/materials.xml
View file

@ -3,7 +3,7 @@
<material id="1">
<density value="7.5" units="g/cc" />
<nuclide name="O-16" xs="70c" ao="1.0" />
<nuclide name="O-16" xs="71c" ao="1.0" />
</material>
</materials>

2
tests/test_lattice/materials.xml
View file

@ -10,7 +10,7 @@
===============================================================
-->
<default_xs>70c</default_xs>
<default_xs>71c</default_xs>
<!-- UO2-PuO2 Mixture -->
<material id="1">

2
tests/test_lattice_multiple/materials.xml
View file

@ -1,7 +1,7 @@
<?xml version="1.0"?>
<materials>
<default_xs>70c</default_xs>
<default_xs>71c</default_xs>
<!-- Fuel composition -->
<material id="1">

2
tests/test_natural_element/materials.xml
View file

@ -3,7 +3,7 @@
<!-- pu-met-fast-021 case 2 -->
<default_xs>70c</default_xs>
<default_xs>71c</default_xs>
<!-- Plutonium -->
<material id="1">

2
tests/test_output/materials.xml
View file

@ -3,7 +3,7 @@
<material id="1">
<density value="4.5" units="g/cc" />
<nuclide name="U-235" xs="70c" ao="1.0" />
<nuclide name="U-235" xs="71c" ao="1.0" />
</material>
</materials>

2
tests/test_particle_restart/materials.xml
View file

@ -3,7 +3,7 @@
<material id="1">
<density value="20.0" units="g/cc" />
<nuclide name="U-235" xs="70c" ao="1.0" />
<nuclide name="U-235" xs="71c" ao="1.0" />
</material>
</materials>

2
tests/test_plot_background/materials.xml
View file

@ -3,7 +3,7 @@
<material id="1">
<density value="4.5" units="g/cc" />
<nuclide name="U-235" xs="70c" ao="1.0" />
<nuclide name="U-235" xs="71c" ao="1.0" />
</material>
</materials>

6
tests/test_plot_basis/materials.xml
View file

@ -3,17 +3,17 @@
<material id="1">
<density value="4.5" units="g/cc" />
<nuclide name="U-235" xs="70c" ao="1.0" />
<nuclide name="U-235" xs="71c" ao="1.0" />
</material>
<material id="2">
<density value="4.5" units="g/cc" />
<nuclide name="U-235" xs="70c" ao="1.0" />
<nuclide name="U-235" xs="71c" ao="1.0" />
</material>
<material id="3">
<density value="4.5" units="g/cc" />
<nuclide name="U-235" xs="70c" ao="1.0" />
<nuclide name="U-235" xs="71c" ao="1.0" />
</material>
</materials>

2
tests/test_plot_colspec/materials.xml
View file

@ -3,7 +3,7 @@
<material id="1">
<density value="4.5" units="g/cc" />
<nuclide name="U-235" xs="70c" ao="1.0" />
<nuclide name="U-235" xs="71c" ao="1.0" />
</material>
</materials>

6
tests/test_plot_mask/materials.xml
View file

@ -3,17 +3,17 @@
<material id="1">
<density value="4.5" units="g/cc" />
<nuclide name="U-235" xs="70c" ao="1.0" />
<nuclide name="U-235" xs="71c" ao="1.0" />
</material>
<material id="2">
<density value="4.5" units="g/cc" />
<nuclide name="U-235" xs="70c" ao="1.0" />
<nuclide name="U-235" xs="71c" ao="1.0" />
</material>
<material id="3">
<density value="4.5" units="g/cc" />
<nuclide name="U-235" xs="70c" ao="1.0" />
<nuclide name="U-235" xs="71c" ao="1.0" />
</material>
</materials>

2
tests/test_ptables_off/materials.xml
View file

@ -3,7 +3,7 @@
<material id="1">
<density value="4.5" units="g/cc" />
<nuclide name="U-235" xs="70c" ao="1.0" />
<nuclide name="U-235" xs="71c" ao="1.0" />
</material>
</materials>

2
tests/test_reflective_cone/materials.xml
View file

@ -3,7 +3,7 @@
<material id="1">
<density value="4.5" units="g/cc" />
<nuclide name="U-235" xs="70c" ao="1.0" />
<nuclide name="U-235" xs="71c" ao="1.0" />
</material>
</materials>

2
tests/test_reflective_cylinder/materials.xml
View file

@ -3,7 +3,7 @@
<material id="1">
<density value="4.5" units="g/cc" />
<nuclide name="U-235" xs="70c" ao="1.0" />
<nuclide name="U-235" xs="71c" ao="1.0" />
</material>
</materials>

2
tests/test_reflective_plane/materials.xml
View file

@ -3,7 +3,7 @@
<material id="1">
<density value="4.5" units="g/cc" />
<nuclide name="U-235" xs="70c" ao="1.0" />
<nuclide name="U-235" xs="71c" ao="1.0" />
</material>
</materials>

2
tests/test_reflective_sphere/materials.xml
View file

@ -3,7 +3,7 @@
<material id="1">
<density value="4.5" units="g/cc" />
<nuclide name="U-235" xs="70c" ao="1.0" />
<nuclide name="U-235" xs="71c" ao="1.0" />
</material>
</materials>

2
tests/test_rotation/materials.xml
View file

@ -3,7 +3,7 @@
<material id="1">
<density value="4.5" units="g/cc" />
<nuclide name="U-235" xs="70c" ao="1.0" />
<nuclide name="U-235" xs="71c" ao="1.0" />
</material>
</materials>

2
tests/test_salphabeta/materials.xml
View file

@ -1,7 +1,7 @@
<?xml version="1.0"?>
<materials>
<default_xs>70c</default_xs>
<default_xs>71c</default_xs>
<material id="1">
<density value="4.5" units="g/cc" />

2
tests/test_salphabeta_multiple/materials.xml
View file

@ -4,7 +4,7 @@
<!-- pu-met-fast-021 case 2, modified to include Zr-H to exercise
the capability to assign a single S(a,b) table to multiple nuclides -->
<default_xs>70c</default_xs>
<default_xs>71c</default_xs>
<!-- Plutonium -->
<material id="1">

2
tests/test_score_MT/materials.xml
View file

@ -1,7 +1,7 @@
<?xml version="1.0"?>
<materials>
<default_xs>70c</default_xs>
<default_xs>71c</default_xs>
<!-- Fuel composition -->
<material id="1">

2
tests/test_score_absorption/materials.xml
View file

@ -1,7 +1,7 @@
<?xml version="1.0"?>
<materials>
<default_xs>70c</default_xs>
<default_xs>71c</default_xs>
<!-- Fuel composition -->
<material id="1">

2
tests/test_score_current/materials.xml
View file

@ -1,7 +1,7 @@
<?xml version="1.0"?>
<materials>
<default_xs>70c</default_xs>
<default_xs>71c</default_xs>
<!-- Fuel composition -->
<material id="1">

2
tests/test_score_events/materials.xml
View file

@ -1,7 +1,7 @@
<?xml version="1.0"?>
<materials>
<default_xs>70c</default_xs>
<default_xs>71c</default_xs>
<!-- Fuel composition -->
<material id="1">

2
tests/test_score_fission/materials.xml
View file

@ -1,7 +1,7 @@
<?xml version="1.0"?>
<materials>
<default_xs>70c</default_xs>
<default_xs>71c</default_xs>
<!-- Fuel composition -->
<material id="1">

2
tests/test_score_flux/materials.xml
View file

@ -1,7 +1,7 @@
<?xml version="1.0"?>
<materials>
<default_xs>70c</default_xs>
<default_xs>71c</default_xs>
<!-- Fuel composition -->
<material id="1">

2
tests/test_score_kappafission/materials.xml
View file

@ -1,7 +1,7 @@
<?xml version="1.0"?>
<materials>
<default_xs>70c</default_xs>
<default_xs>71c</default_xs>
<!-- Fuel composition -->
<material id="1">

2
tests/test_score_nufission/materials.xml
View file

@ -1,7 +1,7 @@
<?xml version="1.0"?>
<materials>
<default_xs>70c</default_xs>
<default_xs>71c</default_xs>
<!-- Fuel composition -->
<material id="1">

2
tests/test_score_nuscatter/materials.xml
View file

@ -1,7 +1,7 @@
<?xml version="1.0"?>
<materials>
<default_xs>70c</default_xs>
<default_xs>71c</default_xs>
<!-- Fuel composition -->
<material id="1">

2
tests/test_score_scatter/materials.xml
View file

@ -1,7 +1,7 @@
<?xml version="1.0"?>
<materials>
<default_xs>70c</default_xs>
<default_xs>71c</default_xs>
<!-- Fuel composition -->
<material id="1">

2
tests/test_score_scatter_n/materials.xml
View file

@ -1,7 +1,7 @@
<?xml version="1.0"?>
<materials>
<default_xs>70c</default_xs>
<default_xs>71c</default_xs>
<!-- Fuel composition -->
<material id="1">

2
tests/test_score_scatter_pn/materials.xml
View file

@ -1,7 +1,7 @@
<?xml version="1.0"?>
<materials>
<default_xs>70c</default_xs>
<default_xs>71c</default_xs>
<!-- Fuel composition -->
<material id="1">

2
tests/test_score_total/materials.xml
View file

@ -1,7 +1,7 @@
<?xml version="1.0"?>
<materials>
<default_xs>70c</default_xs>
<default_xs>71c</default_xs>
<!-- Fuel composition -->
<material id="1">

2
tests/test_seed/materials.xml
View file

@ -3,7 +3,7 @@
<material id="1">
<density value="4.5" units="g/cc" />
<nuclide name="U-235" xs="70c" ao="1.0" />
<nuclide name="U-235" xs="71c" ao="1.0" />
</material>
</materials>

2
tests/test_source_angle_mono/materials.xml
View file

@ -3,7 +3,7 @@
<material id="1">
<density value="4.5" units="g/cc" />
<nuclide name="U-235" xs="70c" ao="1.0" />
<nuclide name="U-235" xs="71c" ao="1.0" />
</material>
</materials>

2
tests/test_source_energy_maxwell/materials.xml
View file

@ -3,7 +3,7 @@
<material id="1">
<density value="4.5" units="g/cc" />
<nuclide name="U-235" xs="70c" ao="1.0" />
<nuclide name="U-235" xs="71c" ao="1.0" />
</material>
</materials>

2
tests/test_source_energy_mono/materials.xml
View file

@ -3,7 +3,7 @@
<material id="1">
<density value="4.5" units="g/cc" />
<nuclide name="U-235" xs="70c" ao="1.0" />
<nuclide name="U-235" xs="71c" ao="1.0" />
</material>
</materials>

2
tests/test_source_file/materials.xml
View file

@ -3,7 +3,7 @@
<material id="1">
<density value="4.5" units="g/cc" />
<nuclide name="U-235" xs="70c" ao="1.0" />
<nuclide name="U-235" xs="71c" ao="1.0" />
</material>
</materials>

2
tests/test_source_point/materials.xml
View file

@ -3,7 +3,7 @@
<material id="1">
<density value="4.5" units="g/cc" />
<nuclide name="U-235" xs="70c" ao="1.0" />
<nuclide name="U-235" xs="71c" ao="1.0" />
</material>
</materials>

2
tests/test_sourcepoint_batch/materials.xml
View file

@ -3,7 +3,7 @@
<material id="1">
<density value="4.5" units="g/cc" />
<nuclide name="U-235" xs="70c" ao="1.0" />
<nuclide name="U-235" xs="71c" ao="1.0" />
</material>
</materials>

2
tests/test_sourcepoint_interval/materials.xml
View file

@ -3,7 +3,7 @@
<material id="1">
<density value="4.5" units="g/cc" />
<nuclide name="U-235" xs="70c" ao="1.0" />
<nuclide name="U-235" xs="71c" ao="1.0" />
</material>
</materials>

2
tests/test_sourcepoint_latest/materials.xml
View file

@ -3,7 +3,7 @@
<material id="1">
<density value="4.5" units="g/cc" />
<nuclide name="U-235" xs="70c" ao="1.0" />
<nuclide name="U-235" xs="71c" ao="1.0" />
</material>
</materials>

2
tests/test_sourcepoint_restart/materials.xml
View file

@ -3,7 +3,7 @@
<material id="1">
<density value="4.5" units="g/cc" />
<nuclide name="U-235" xs="70c" ao="1.0" />
<nuclide name="U-235" xs="71c" ao="1.0" />
</material>
</materials>

2
tests/test_statepoint_batch/materials.xml
View file

@ -3,7 +3,7 @@
<material id="1">
<density value="4.5" units="g/cc" />
<nuclide name="U-235" xs="70c" ao="1.0" />
<nuclide name="U-235" xs="71c" ao="1.0" />
</material>
</materials>

2
tests/test_statepoint_interval/materials.xml
View file

@ -3,7 +3,7 @@
<material id="1">
<density value="4.5" units="g/cc" />
<nuclide name="U-235" xs="70c" ao="1.0" />
<nuclide name="U-235" xs="71c" ao="1.0" />
</material>
</materials>

2
tests/test_statepoint_restart/materials.xml
View file

@ -3,7 +3,7 @@
<material id="1">
<density value="4.5" units="g/cc" />
<nuclide name="U-235" xs="70c" ao="1.0" />
<nuclide name="U-235" xs="71c" ao="1.0" />
</material>
</materials>

2
tests/test_statepoint_sourcesep/materials.xml
View file

@ -3,7 +3,7 @@
<material id="1">
<density value="4.5" units="g/cc" />
<nuclide name="U-235" xs="70c" ao="1.0" />
<nuclide name="U-235" xs="71c" ao="1.0" />
</material>
</materials>

4
tests/test_survival_biasing/materials.xml
View file

@ -3,8 +3,8 @@
<material id="1">
<density value="19.5" units="g/cc" />
<nuclide name="U-235" xs="70c" ao="2.0" />
<nuclide name="U-238" xs="70c" ao="1.0" />
<nuclide name="U-235" xs="71c" ao="2.0" />
<nuclide name="U-238" xs="71c" ao="1.0" />
</material>
</materials>

2
tests/test_tally_assumesep/materials.xml
View file

@ -1,7 +1,7 @@
<?xml version="1.0"?>
<materials>
<default_xs>70c</default_xs>
<default_xs>71c</default_xs>
<!-- Fuel composition -->
<material id="1">

2
tests/test_trace/materials.xml
View file

@ -3,7 +3,7 @@
<material id="1">
<density value="4.5" units="g/cc" />
<nuclide name="U-235" xs="70c" ao="1.0" />
<nuclide name="U-235" xs="71c" ao="1.0" />
</material>
</materials>

92
tests/test_track_output/materials.xml
View file

@ -4,27 +4,27 @@
<!-- material 1: Water with 1511 PPM -->
<material id="1">
<density value="0.99823" units="g/cc" />
<nuclide name="H-1" xs="70c" ao="6.6737E-002" />
<nuclide name="O-16" xs="70c" ao="3.3369E-002" />
<nuclide name="B-10" xs="70c" ao="1.6769E-005" />
<nuclide name="B-11" xs="70c" ao="6.7497E-005" />
<nuclide name="H-1" xs="71c" ao="6.6737E-002" />
<nuclide name="O-16" xs="71c" ao="3.3369E-002" />
<nuclide name="B-10" xs="71c" ao="1.6769E-005" />
<nuclide name="B-11" xs="71c" ao="6.7497E-005" />
<sab name="lwtr" xs="10t" />
</material>
<!-- material 2: Fuel (2.459 w/o with B-10 for impurities) -->
<material id="2">
<density value="10.24" units="g/cc" />
<nuclide name="U-235" xs="70c" ao="5.6868E-004" />
<!-- <nuclide name="U-234" xs="70c" ao="4.5689E-006" /> -->
<nuclide name="U-238" xs="70c" ao="2.2268E-002" />
<nuclide name="O-16" xs="70c" ao="4.5683E-002" />
<nuclide name="B-10" xs="70c" ao="2.6055E-007" />
<nuclide name="U-235" xs="71c" ao="5.6868E-004" />
<!-- <nuclide name="U-234" xs="71c" ao="4.5689E-006" /> -->
<nuclide name="U-238" xs="71c" ao="2.2268E-002" />
<nuclide name="O-16" xs="71c" ao="4.5683E-002" />
<nuclide name="B-10" xs="71c" ao="2.6055E-007" />
</material>
<!-- Zircaloy-4 -->
<material id="3">
<density value=" 6.55" units="g/cc" />
<nuclide name="O-16" xs="70c" ao="3.0743e-04" />
<nuclide name="O-16" xs="71c" ao="3.0743e-04" />
<!-- <nuclide name="O-17" xs="71c" ao="7.4887e-07" />-->
<!-- <nuclide name="Cr-50" xs="71c" ao="3.2962e-06" />-->
<!-- <nuclide name="Cr-52" xs="71c" ao="6.3564e-05" />-->
@ -34,11 +34,11 @@
<!-- <nuclide name="Fe-56" xs="71c" ao="1.3610e-04" />-->
<!-- <nuclide name="Fe-57" xs="71c" ao="3.1431e-06" />-->
<!-- <nuclide name="Fe-58" xs="71c" ao="4.1829e-07" />-->
<nuclide name="Zr-90" xs="70c" ao="2.1827e-02" />
<nuclide name="Zr-91" xs="70c" ao="4.7600e-03" />
<nuclide name="Zr-92" xs="70c" ao="7.2758e-03" />
<nuclide name="Zr-94" xs="70c" ao="7.3734e-03" />
<nuclide name="Zr-96" xs="70c" ao="1.1879e-03" />
<nuclide name="Zr-90" xs="71c" ao="2.1827e-02" />
<nuclide name="Zr-91" xs="71c" ao="4.7600e-03" />
<nuclide name="Zr-92" xs="71c" ao="7.2758e-03" />
<nuclide name="Zr-94" xs="71c" ao="7.3734e-03" />
<nuclide name="Zr-96" xs="71c" ao="1.1879e-03" />
<!-- <nuclide name="Sn-112" xs="71c" ao="4.6735e-06" />-->
<!-- <nuclide name="Sn-114" xs="71c" ao="3.1799e-06" />-->
<!-- <nuclide name="Sn-115" xs="71c" ao="1.6381e-06" />-->
@ -54,42 +54,42 @@
<!-- material 3: Fuel Aluminum 6061 cladding -->
<!-- <material id="3">-->
<!-- <density value="2.5052" units="g/cc" />-->
<!-- <nuclide name="Al-27" xs="70c" ao="5.3985e-02" />-->
<!-- <nuclide name="Mn-55" xs="70c" ao="4.1191e-05" />-->
<!-- <nuclide name="Mg-24" xs="70c" ao="4.9031e-04" />-->
<!-- <nuclide name="Mg-25" xs="70c" ao="6.2072e-05" />-->
<!-- <nuclide name="Mg-26" xs="70c" ao="6.8341e-05" />-->
<!-- <nuclide name="Si-28" xs="70c" ao="2.9726e-04" />-->
<!-- <nuclide name="Si-29" xs="70c" ao="1.5094e-05" />-->
<!-- <nuclide name="Si-30" xs="70c" ao="9.9499e-06" />-->
<!-- <nuclide name="Cr-50" xs="70c" ao="2.5214e-06" />-->
<!-- <nuclide name="Cr-52" xs="70c" ao="4.8622e-05" />-->
<!-- <nuclide name="Cr-53" xs="70c" ao="5.5133e-06" />-->
<!-- <nuclide name="Cr-54" xs="70c" ao="1.3724e-06" />-->
<!-- <nuclide name="Fe-54" xs="70c" ao="1.1053e-05" />-->
<!-- <nuclide name="Fe-56" xs="70c" ao="1.7351e-04" />-->
<!-- <nuclide name="Fe-57" xs="70c" ao="4.0070e-06" />-->
<!-- <nuclide name="Fe-58" xs="70c" ao="5.3326e-07" />-->
<!-- <nuclide name="Ti-46" xs="70c" ao="3.8992e-06" />-->
<!-- <nuclide name="Ti-47" xs="70c" ao="3.5164e-06" />-->
<!-- <nuclide name="Ti-48" xs="70c" ao="3.4842e-05" />-->
<!-- <nuclide name="Ti-49" xs="70c" ao="2.5569e-06" />-->
<!-- <nuclide name="Ti-50" xs="70c" ao="2.4482e-06" />-->
<!-- <nuclide name="Cu-63" xs="70c" ao="4.1054e-05" />-->
<!-- <nuclide name="Cu-65" xs="70c" ao="1.8299e-05" />-->
<!-- <nuclide name="Al-27" xs="71c" ao="5.3985e-02" />-->
<!-- <nuclide name="Mn-55" xs="71c" ao="4.1191e-05" />-->
<!-- <nuclide name="Mg-24" xs="71c" ao="4.9031e-04" />-->
<!-- <nuclide name="Mg-25" xs="71c" ao="6.2072e-05" />-->
<!-- <nuclide name="Mg-26" xs="71c" ao="6.8341e-05" />-->
<!-- <nuclide name="Si-28" xs="71c" ao="2.9726e-04" />-->
<!-- <nuclide name="Si-29" xs="71c" ao="1.5094e-05" />-->
<!-- <nuclide name="Si-30" xs="71c" ao="9.9499e-06" />-->
<!-- <nuclide name="Cr-50" xs="71c" ao="2.5214e-06" />-->
<!-- <nuclide name="Cr-52" xs="71c" ao="4.8622e-05" />-->
<!-- <nuclide name="Cr-53" xs="71c" ao="5.5133e-06" />-->
<!-- <nuclide name="Cr-54" xs="71c" ao="1.3724e-06" />-->
<!-- <nuclide name="Fe-54" xs="71c" ao="1.1053e-05" />-->
<!-- <nuclide name="Fe-56" xs="71c" ao="1.7351e-04" />-->
<!-- <nuclide name="Fe-57" xs="71c" ao="4.0070e-06" />-->
<!-- <nuclide name="Fe-58" xs="71c" ao="5.3326e-07" />-->
<!-- <nuclide name="Ti-46" xs="71c" ao="3.8992e-06" />-->
<!-- <nuclide name="Ti-47" xs="71c" ao="3.5164e-06" />-->
<!-- <nuclide name="Ti-48" xs="71c" ao="3.4842e-05" />-->
<!-- <nuclide name="Ti-49" xs="71c" ao="2.5569e-06" />-->
<!-- <nuclide name="Ti-50" xs="71c" ao="2.4482e-06" />-->
<!-- <nuclide name="Cu-63" xs="71c" ao="4.1054e-05" />-->
<!-- <nuclide name="Cu-65" xs="71c" ao="1.8299e-05" />-->
<!-- </material>-->
<!-- material 4: Control Rod Material -->
<material id="4">
<density value="2.2442" units="g/cc" />
<nuclide name="B-10" xs="70c" ao="9.7491e-4" />
<nuclide name="B-11" xs="70c" ao="3.9241e-3" />
<nuclide name="O-16" xs="70c" ao="4.4829e-2" />
<!-- <nuclide name="Na-23" xs="70c" ao="1.7444e-3" />-->
<!-- <nuclide name="Al-27" xs="70c" ao="1.0018e-3" />-->
<!-- <nuclide name="Si-28" xs="70c" ao="1.6884e-02" />-->
<!-- <nuclide name="Si-29" xs="70c" ao="8.5730e-04" />-->
<!-- <nuclide name="Si-30" xs="70c" ao="5.6513e-04" />-->
<nuclide name="B-10" xs="71c" ao="9.7491e-4" />
<nuclide name="B-11" xs="71c" ao="3.9241e-3" />
<nuclide name="O-16" xs="71c" ao="4.4829e-2" />
<!-- <nuclide name="Na-23" xs="71c" ao="1.7444e-3" />-->
<!-- <nuclide name="Al-27" xs="71c" ao="1.0018e-3" />-->
<!-- <nuclide name="Si-28" xs="71c" ao="1.6884e-02" />-->
<!-- <nuclide name="Si-29" xs="71c" ao="8.5730e-04" />-->
<!-- <nuclide name="Si-30" xs="71c" ao="5.6513e-04" />-->
</material>
</materials>

2
tests/test_translation/materials.xml
View file

@ -3,7 +3,7 @@
<material id="1">
<density value="4.5" units="g/cc" />
<nuclide name="U-235" xs="70c" ao="1.0" />
<nuclide name="U-235" xs="71c" ao="1.0" />
</material>
</materials>

2
tests/test_uniform_fs/materials.xml
View file

@ -3,7 +3,7 @@
<material id="1">
<density value="4.5" units="g/cc" />
<nuclide name="U-235" xs="70c" ao="1.0" />
<nuclide name="U-235" xs="71c" ao="1.0" />
</material>
</materials>

2
tests/test_universe/materials.xml
View file

@ -3,7 +3,7 @@
<material id="1">
<density value="4.5" units="g/cc" />
<nuclide name="U-235" xs="70c" ao="1.0" />
<nuclide name="U-235" xs="71c" ao="1.0" />
</material>
</materials>

2
tests/test_void/materials.xml
View file

@ -3,7 +3,7 @@
<!-- pu-met-fast-019 -->
<default_xs>70c</default_xs>
<default_xs>71c</default_xs>
<!-- Plutonium -->
<material id="1">