crp/OpenMC
1
0
Fork 0
mirror of https://github.com/openmc-dev/openmc.git synced 2026-07-28 22:26:08 -04:00
Code Issues Projects Releases Packages Wiki Activity Actions 5

Merged branch xml into master.

Browse source
This commit is contained in:
Paul Romano 2011-09-01 22:48:55 -04:00
parent b451da7b44
commit 865c3a4eb7
31 changed files with 3848 additions and 1109 deletions
Download patch file Download diff file Expand all files Collapse all files

41
examples/basic/geometry.xml Normal file
View file

@ -0,0 +1,41 @@
<?xml version="1.0" encoding="UTF-8"?>
<geometry>
<!-- Definition of Cells -->
<cell uid="1">
<universe>0</universe>
<fill>37</fill>
<surfaces>-2</surfaces>
</cell>
<cell uid="100">
<universe>37</universe>
<material>40</material>
<surfaces>-1</surfaces>
</cell>
<cell uid="101">
<universe>37</universe>
<material>41</material>
<surfaces>1</surfaces>
</cell>
<cell uid="2">
<universe>0</universe>
<material>41</material>
<surfaces>2 -3</surfaces>
</cell>
<!-- Defition of Surfaces -->
<surface uid="1">
<type>z-cylinder</type>
<coeffs>0 0 7</coeffs>
</surface>
<surface uid="2">
<type>z-cylinder</type>
<coeffs>0 0 9</coeffs>
</surface>
<surface uid="3">
<type>z-cylinder</type>
<coeffs>0 0 11</coeffs>
<boundary>vacuum</boundary>
</surface>
</geometry>

17
examples/basic/material.xml Normal file
View file

@ -0,0 +1,17 @@
<?xml version="1.0"?>
<materials>
<!-- Definition of materials -->
<material uid="40">
<density value="4.5" units="g/cc" />
<nuclide name="U-235" xs="03c" ao="1.0" />
</material>
<material uid="41">
<density value="1.0" units="g/cc" />
<nuclide name="H-1" xs="03c" ao="2.0" />
<nuclide name="O-16" xs="03c" ao="1.0" />
<sab uid="H-H2O" xs="10t" />
</material>
</materials>

23
examples/basic/settings.xml Normal file
View file

@ -0,0 +1,23 @@
<?xml version="1.0" encoding="UTF-8"?>
<settings>
<!-- Path for cross section library -->
<xslibrary path="/opt/serpent/xsdata/endfb7" />
<!-- Parameters for criticality calculation -->
<criticality>
<cycles>15</cycles>
<inactive>5</inactive>
<particles>10000</particles>
</criticality>
<!-- How verbose output should be -->
<verbosity value="7" />
<!-- Starting source -->
<source>
<type>box</type>
<coeffs>-4 -4 -4 4 4 4</coeffs>
</source>
</settings>

18
examples/basic/tallies.xml Normal file
View file

@ -0,0 +1,18 @@
<?xml version="1.0"?>
<tallies>
<tally id="1">
<!-- this is where you specify filters -->
<filters>
<region>1</region>
<energy>0.0 0.625 20.0e6</energy>
</filters>
<!-- which reactions to score -->
<reactions>1 2 -4 -8</reactions>
<!-- which nuclides to score -->
<nuclides>U-238</nuclides>
</tally>
</tallies>