From 79f792c09a7e0ef72584f350fe79ad96bdeae847 Mon Sep 17 00:00:00 2001
From: "dr.yuri" <dr.yuri92@gmail.com>
Date: Thu, 30 May 2019 10:54:08 +0300
Subject: [PATCH] New regression test for lattice with OX orient

---
 .../lattice_hex_OX/__init__.py                |   0
 .../lattice_hex_OX/inputs_true.dat            | 126 +++++++++++++
 .../lattice_hex_OX/results_true.dat           |   2 +
 tests/regression_tests/lattice_hex_OX/test.py | 171 ++++++++++++++++++
 4 files changed, 299 insertions(+)
 create mode 100644 tests/regression_tests/lattice_hex_OX/__init__.py
 create mode 100644 tests/regression_tests/lattice_hex_OX/inputs_true.dat
 create mode 100644 tests/regression_tests/lattice_hex_OX/results_true.dat
 create mode 100644 tests/regression_tests/lattice_hex_OX/test.py

diff --git a/tests/regression_tests/lattice_hex_OX/__init__.py b/tests/regression_tests/lattice_hex_OX/__init__.py
new file mode 100644
index 0000000000..e69de29bb2
diff --git a/tests/regression_tests/lattice_hex_OX/inputs_true.dat b/tests/regression_tests/lattice_hex_OX/inputs_true.dat
new file mode 100644
index 0000000000..9130cf284d
--- /dev/null
+++ b/tests/regression_tests/lattice_hex_OX/inputs_true.dat
@@ -0,0 +1,126 @@
+<?xml version='1.0' encoding='utf-8'?>
+<geometry>
+  <cell id="1" material="1" region="-1" universe="1" />
+  <cell id="2" material="4" region="-2 1" universe="1" />
+  <cell id="3" material="2" region="2" universe="1" />
+  <cell id="4" material="2" region="-3" universe="2" />
+  <cell id="5" material="4" region="-4 3" universe="2" />
+  <cell id="6" material="2" region="4" universe="2" />
+  <cell id="7" material="3" region="-5" universe="3" />
+  <cell id="8" material="4" region="-6 5" universe="3" />
+  <cell id="9" material="2" region="-7 6" universe="3" />
+  <cell id="10" material="4" region="-8 7" universe="3" />
+  <cell id="11" material="2" region="8" universe="3" />
+  <cell id="12" material="2" universe="4" />
+  <cell fill="9" id="13" name="container assembly cell" region="-11 12 -13 14 15 -16 9 -10" universe="5" />
+  <hex_lattice id="9" n_axial="2" n_rings="11" name="regular fuel assembly" orient="OX">
+    <pitch>1.235 5.0</pitch>
+    <outer>4</outer>
+    <center>0.0 0.0 5.0</center>
+    <universes>
+          1 1 1 1 1 1 1 1 1 1 1
+         1 1 1 1 1 1 1 1 1 1 1 1
+        1 1 1 1 1 1 1 1 1 1 1 1 1
+       1 1 1 1 1 1 1 1 1 1 1 1 1 1
+      1 1 1 1 1 1 1 3 1 1 1 1 1 1 1
+     1 1 1 1 1 3 1 1 1 1 3 1 1 1 1 1
+    1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
+   1 1 1 1 3 1 1 1 1 3 1 1 1 3 1 1 1 1
+  1 1 1 1 1 1 1 3 1 1 1 1 1 1 1 1 1 1 1
+ 1 1 1 1 1 1 1 1 1 1 1 1 3 1 1 1 1 1 1 1
+1 1 1 1 1 3 1 1 1 1 2 1 1 1 1 3 1 1 1 1 1
+ 1 1 1 1 1 1 1 3 1 1 1 1 1 1 1 1 1 1 1 1
+  1 1 1 1 1 1 1 1 1 1 1 3 1 1 1 1 1 1 1
+   1 1 1 1 3 1 1 1 3 1 1 1 1 3 1 1 1 1
+    1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
+     1 1 1 1 1 3 1 1 1 1 3 1 1 1 1 1
+      1 1 1 1 1 1 1 3 1 1 1 1 1 1 1
+       1 1 1 1 1 1 1 1 1 1 1 1 1 1
+        1 1 1 1 1 1 1 1 1 1 1 1 1
+         1 1 1 1 1 1 1 1 1 1 1 1
+          1 1 1 1 1 1 1 1 1 1 1
+          1 1 1 1 1 1 1 1 1 1 1
+         1 1 1 1 1 1 1 1 1 1 1 1
+        1 1 1 1 1 1 1 1 1 1 1 1 1
+       1 1 1 1 1 1 1 1 1 1 1 1 1 1
+      1 1 1 1 1 1 1 3 1 1 1 1 1 1 1
+     1 1 1 1 1 3 1 1 1 1 3 1 1 1 1 1
+    1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
+   1 1 1 1 3 1 1 1 1 3 1 1 1 3 1 1 1 1
+  1 1 1 1 1 1 1 3 1 1 1 1 1 1 1 1 1 1 1
+ 1 1 1 1 1 1 1 1 1 1 1 1 3 1 1 1 1 1 1 1
+1 1 1 1 1 3 1 1 1 1 2 1 1 1 1 3 1 1 1 1 1
+ 1 1 1 1 1 1 1 3 1 1 1 1 1 1 1 1 1 1 1 1
+  1 1 1 1 1 1 1 1 1 1 1 3 1 1 1 1 1 1 1
+   1 1 1 1 3 1 1 1 3 1 1 1 1 3 1 1 1 1
+    1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
+     1 1 1 1 1 3 1 1 1 1 3 1 1 1 1 1
+      1 1 1 1 1 1 1 3 1 1 1 1 1 1 1
+       1 1 1 1 1 1 1 1 1 1 1 1 1 1
+        1 1 1 1 1 1 1 1 1 1 1 1 1
+         1 1 1 1 1 1 1 1 1 1 1 1
+          1 1 1 1 1 1 1 1 1 1 1</universes>
+  </hex_lattice>
+  <surface coeffs="0.0 0.0 0.386" id="1" type="z-cylinder" />
+  <surface coeffs="0.0 0.0 0.4582" id="2" type="z-cylinder" />
+  <surface coeffs="0.0 0.0 0.45" id="3" type="z-cylinder" />
+  <surface coeffs="0.0 0.0 0.5177" id="4" type="z-cylinder" />
+  <surface coeffs="0.0 0.0 0.35" id="5" type="z-cylinder" />
+  <surface coeffs="0.0 0.0 0.41" id="6" type="z-cylinder" />
+  <surface coeffs="0.0 0.0 0.545" id="7" type="z-cylinder" />
+  <surface coeffs="0.0 0.0 0.6323" id="8" type="z-cylinder" />
+  <surface boundary="reflective" coeffs="0.0" id="9" type="z-plane" />
+  <surface boundary="reflective" coeffs="10.0" id="10" type="z-plane" />
+  <surface boundary="reflective" coeffs="11.8" id="11" type="y-plane" />
+  <surface boundary="reflective" coeffs="-11.8" id="12" type="y-plane" />
+  <surface boundary="reflective" coeffs="1.7320508075688772 1.0 0.0 23.6" id="13" type="plane" />
+  <surface boundary="reflective" coeffs="-1.7320508075688772 1.0 0.0 -23.6" id="14" type="plane" />
+  <surface boundary="reflective" coeffs="1.7320508075688772 1.0 0.0 -23.6" id="15" type="plane" />
+  <surface boundary="reflective" coeffs="-1.7320508075688772 1.0 0.0 23.6" id="16" type="plane" />
+</geometry>
+<?xml version='1.0' encoding='utf-8'?>
+<materials>
+  <material depletable="true" id="1" name="UO2">
+    <density units="sum" />
+    <nuclide ao="0.0008737" name="U235" />
+    <nuclide ao="0.018744" name="U238" />
+    <nuclide ao="0.039235" name="O16" />
+  </material>
+  <material id="2" name="borated H2O">
+    <density units="sum" />
+    <nuclide ao="0.06694" name="H1" />
+    <nuclide ao="0.03347" name="O16" />
+    <nuclide ao="6.6262e-06" name="B10" />
+    <nuclide ao="2.6839e-05" name="B11" />
+  </material>
+  <material id="3" name="pellet B4C">
+    <density units="sum" />
+    <nuclide ao="0.01966" name="C0" />
+    <nuclide ao="4.7344e-06" name="B11" />
+    <nuclide ao="1.9177e-05" name="B10" />
+  </material>
+  <material id="4" name="Zirc4">
+    <density units="sum" />
+    <nuclide ao="0.021763349999999997" name="Zr90" />
+    <nuclide ao="0.00474606" name="Zr91" />
+    <nuclide ao="0.00725445" name="Zr92" />
+    <nuclide ao="0.00735174" name="Zr94" />
+    <nuclide ao="0.0011844" name="Zr96" />
+  </material>
+</materials>
+<?xml version='1.0' encoding='utf-8'?>
+<settings>
+  <run_mode>eigenvalue</run_mode>
+  <particles>1000</particles>
+  <batches>10</batches>
+  <inactive>5</inactive>
+  <source strength="1.0">
+    <space type="box">
+      <parameters>-13.62546635287517 -13.62546635287517 0.0 13.62546635287517 13.62546635287517 10.0</parameters>
+    </space>
+  </source>
+  <output>
+    <summary>false</summary>
+  </output>
+  <seed>22</seed>
+</settings>
diff --git a/tests/regression_tests/lattice_hex_OX/results_true.dat b/tests/regression_tests/lattice_hex_OX/results_true.dat
new file mode 100644
index 0000000000..a742aa0d54
--- /dev/null
+++ b/tests/regression_tests/lattice_hex_OX/results_true.dat
@@ -0,0 +1,2 @@
+k-combined:
+1.355663E+00 2.896562E-02
diff --git a/tests/regression_tests/lattice_hex_OX/test.py b/tests/regression_tests/lattice_hex_OX/test.py
new file mode 100644
index 0000000000..2eab458dca
--- /dev/null
+++ b/tests/regression_tests/lattice_hex_OX/test.py
@@ -0,0 +1,171 @@
+from tests.testing_harness import PyAPITestHarness
+import openmc
+import numpy as np
+
+class HexLatticeOXTestHarness(PyAPITestHarness):
+    def _build_inputs(self):
+        materials = openmc.Materials()
+
+        fuel_mat = openmc.Material(material_id=1,name="UO2")
+        fuel_mat.set_density('sum')
+        fuel_mat.add_nuclide('U235',0.87370e-03)
+        fuel_mat.add_nuclide('U238',1.87440e-02)
+        fuel_mat.add_nuclide('O16',3.92350e-02)
+        materials.append(fuel_mat)
+
+        coolant = openmc.Material(material_id=2,name="borated H2O")
+        coolant.set_density('sum')
+        coolant.add_nuclide('H1',0.06694)
+        coolant.add_nuclide('O16',0.03347)
+        coolant.add_nuclide('B10',6.6262e-6)
+        coolant.add_nuclide('B11',2.6839e-5)
+        materials.append(coolant)
+
+        absorber = openmc.Material(material_id=3,name="pellet B4C")
+        absorber.set_density('sum')
+        absorber.add_nuclide('C0',0.01966)
+        absorber.add_nuclide('B11',4.7344e-6)
+        absorber.add_nuclide('B10',1.9177e-5)
+        materials.append(absorber)
+
+        zirc = openmc.Material(material_id=4,name="Zirc4")
+        zirc.set_density('sum')
+        zirc.add_element('Zr',4.23e-2)
+        materials.append(zirc)
+
+        materials.export_to_xml()
+
+        ### Geometry ###
+        pin_rad = 0.7 # cm
+        assembly_pitch = 1.235 # cm
+        hexagonal_pitch = 23.6 # cm
+        length = 10.0 # cm
+        #Fuel pin surfaces
+        cylfuelin = openmc.ZCylinder(surface_id=1,r=0.386)
+        cylfuelout = openmc.ZCylinder(surface_id=2,r=0.4582)
+        #Fuel cells
+        infcell = openmc.Cell(cell_id=1)
+        infcell.region = -cylfuelin
+        infcell.fill = fuel_mat
+
+        clfcell = openmc.Cell(cell_id=2)
+        clfcell.region = -cylfuelout & +cylfuelin
+        clfcell.fill = zirc
+
+        outfcell = openmc.Cell(cell_id=3)
+        outfcell.region = +cylfuelout
+        outfcell.fill = coolant
+        #Fuel universe
+        fuel_ch_univ = openmc.Universe(universe_id=1,name="Fuel channel",cells=[infcell, clfcell,outfcell])  
+  
+        #Central tube surfaces
+        cyltubein = openmc.ZCylinder(surface_id=3,r=0.45)
+        cyltubeout = openmc.ZCylinder(surface_id=4,r=0.5177)
+        #Central tube cells
+        inctcell = openmc.Cell(cell_id=4)
+        inctcell.region = -cyltubein
+        inctcell.fill = coolant
+
+        clctcell = openmc.Cell(cell_id=5)
+        clctcell.region = -cyltubeout & +cyltubein
+        clctcell.fill = zirc
+
+        outctcell = openmc.Cell(cell_id=6)
+        outctcell.region = +cyltubeout
+        outctcell.fill = coolant
+        #Central tubel universe
+        tube_ch_univ = openmc.Universe(universe_id=2,name="Central tube channel",cells=[inctcell, clctcell,outctcell])    
+
+        #Absorber tube surfaces
+        cylabsin = openmc.ZCylinder(surface_id=5,r=0.35)
+        cylabsout = openmc.ZCylinder(surface_id=6,r=0.41)
+        cylabsclin = openmc.ZCylinder(surface_id=7,r=0.545)
+        cylabsclout = openmc.ZCylinder(surface_id=8,r=0.6323)
+        #Absorber tube cells
+        inabscell = openmc.Cell(cell_id=7)
+        inabscell.region = -cylabsin
+        inabscell.fill = absorber
+
+        clabscell = openmc.Cell(cell_id=8)
+        clabscell.region = -cylabsout & +cylabsin
+        clabscell.fill = zirc
+
+        interabscell = openmc.Cell(cell_id=9)
+        interabscell.region = -cylabsclin & +cylabsout
+        interabscell.fill = coolant
+  
+        clatcell = openmc.Cell(cell_id=10)
+        clatcell.region = -cylabsclout & +cylabsclin
+        clatcell.fill = zirc
+
+        outabscell = openmc.Cell(cell_id=11)
+        outabscell.region = +cylabsclout
+        outabscell.fill = coolant
+        #Absorber tube universe
+        abs_ch_univ = openmc.Universe(universe_id=3,name="Central tube channel",cells=[inabscell,clabscell,interabscell,clatcell,outabscell])
+        #Assembly surfaces
+        edge_length = (1./np.sqrt(3.0)) * hexagonal_pitch 
+        fuel_bottom = openmc.ZPlane(surface_id=9,z0=0.0, boundary_type = 'reflective')
+        fuel_top = openmc.ZPlane(surface_id=10,z0=length, boundary_type = 'reflective')
+        # a hex surface for the core to go inside of
+        hexprism = openmc.model.get_hexagonal_prism(edge_length=edge_length,
+                                                    origin=(0.0, 0.0),
+                                                    boundary_type = 'reflective',
+                                                    orientation='x')
+        region = hexprism & +fuel_bottom & -fuel_top
+
+        inf_mat = openmc.Cell(cell_id=12)
+        inf_mat.fill = coolant
+        inf_mat_univ = openmc.Universe(universe_id=4,cells=[inf_mat,])
+        # Fill lattice by channels
+        nring = 11
+        universes = [] # array of rings
+        for ring in range(nring - 1,-1,-1):
+            arr = []
+            arr.append(fuel_ch_univ)
+            for cell in range(ring * 6 - 1):
+                arr.append(fuel_ch_univ)
+            universes.append(arr)
+        universes[-1] = [tube_ch_univ]
+        channels = [(7,16),(7,13),(7,10),(7,7),(7,4),(7,1),(5,0),\
+        (4,33),(5,25),(4,27),(5,20),(4,21),(5,15),\
+        (4,15),(5,10),(4,9),(5,5),(4,3)]
+        for i,j in channels:
+            universes[i][j] = abs_ch_univ
+        lattice = openmc.HexLattice(name="regular fuel assembly")
+        lattice.orientation = "ox"
+        lattice.center = (0., 0., length/2.0)
+        lattice.pitch = (assembly_pitch,length/2.0)
+        lattice.universes = 2*[universes]
+        lattice.outer = inf_mat_univ
+       
+        assembly_cell = openmc.Cell(cell_id=13,name="container assembly cell")
+        assembly_cell.region = region
+        assembly_cell.fill = lattice
+
+        root_univ = openmc.Universe(universe_id=5,name="root universe", cells=[assembly_cell,])
+
+        geom = openmc.Geometry(root_univ)
+        geom.export_to_xml()
+
+        ### Settings ###
+
+        settings = openmc.Settings()
+        settings.run_mode = 'eigenvalue'
+
+        source = openmc.Source()
+        ll = [-edge_length, -edge_length, 0.0]
+        ur = [edge_length, edge_length, 10.0]
+        source.space = openmc.stats.Box(ll, ur)
+        source.strength = 1.0
+        settings.source = source
+        settings.output = {'summary' : False}
+        settings.batches = 10
+        settings.inactive = 5
+        settings.particles = 1000
+        settings.seed = 22
+        settings.export_to_xml()
+
+def test_lattice_hex_ox_surf():
+    harness = HexLatticeOXTestHarness('statepoint.10.h5')
+    harness.main()