From 61fb8194a530ae3ebc1345607899d18371cf257c Mon Sep 17 00:00:00 2001
From: Adam Nelson <nelsonag@umich.edu>
Date: Sun, 29 May 2016 10:42:20 -0400
Subject: [PATCH] Added a test which tests creating MGXS in CE mode and piping
 in to MG mode.

---
 openmc/mgxs/library.py                        |  2 +-
 .../inputs_true.dat                           |  1 +
 .../results_true.dat                          |  2 +
 .../test_mgxs_library_ce_to_mg.py             | 93 +++++++++++++++++++
 4 files changed, 97 insertions(+), 1 deletion(-)
 create mode 100644 tests/test_mgxs_library_ce_to_mg/inputs_true.dat
 create mode 100644 tests/test_mgxs_library_ce_to_mg/results_true.dat
 create mode 100644 tests/test_mgxs_library_ce_to_mg/test_mgxs_library_ce_to_mg.py

diff --git a/openmc/mgxs/library.py b/openmc/mgxs/library.py
index 4c2497173e..62dde28ab2 100644
--- a/openmc/mgxs/library.py
+++ b/openmc/mgxs/library.py
@@ -34,7 +34,7 @@ class Library(object):
     Parameters
     ----------
     openmc_geometry : openmc.Geometry
-        An geometry which has been initialized with a root universe
+        A geometry which has been initialized with a root universe
     by_nuclide : bool
         If true, computes cross sections for each nuclide in each domain
     mgxs_types : Iterable of str
diff --git a/tests/test_mgxs_library_ce_to_mg/inputs_true.dat b/tests/test_mgxs_library_ce_to_mg/inputs_true.dat
new file mode 100644
index 0000000000..ad4b639655
--- /dev/null
+++ b/tests/test_mgxs_library_ce_to_mg/inputs_true.dat
@@ -0,0 +1 @@
+15355a90181bc3a8ba70bcc9a89beff2c240dc75abbf26c3e3b6a940c4ec2028b238422ac26af08863c24ce6fc16d48d249f17cd0bce53df0141138deccfc81a
\ No newline at end of file
diff --git a/tests/test_mgxs_library_ce_to_mg/results_true.dat b/tests/test_mgxs_library_ce_to_mg/results_true.dat
new file mode 100644
index 0000000000..1152dd2cca
--- /dev/null
+++ b/tests/test_mgxs_library_ce_to_mg/results_true.dat
@@ -0,0 +1,2 @@
+k-combined:
+1.017325E+00 3.827758E-02
diff --git a/tests/test_mgxs_library_ce_to_mg/test_mgxs_library_ce_to_mg.py b/tests/test_mgxs_library_ce_to_mg/test_mgxs_library_ce_to_mg.py
new file mode 100644
index 0000000000..9bf70bbbbe
--- /dev/null
+++ b/tests/test_mgxs_library_ce_to_mg/test_mgxs_library_ce_to_mg.py
@@ -0,0 +1,93 @@
+#!/usr/bin/env python
+
+import os
+import sys
+import glob
+import hashlib
+sys.path.insert(0, os.pardir)
+from testing_harness import PyAPITestHarness
+import openmc
+import openmc.mgxs
+
+
+class MGXSTestHarness(PyAPITestHarness):
+    def _build_inputs(self):
+
+        # The openmc.mgxs module needs a summary.h5 file
+        self._input_set.settings.output = {'summary': True}
+
+        # Generate inputs using parent class routine
+        super(MGXSTestHarness, self)._build_inputs()
+
+        # Initialize a two-group structure
+        energy_groups = openmc.mgxs.EnergyGroups(group_edges=[0, 0.625e-6, 20.])
+
+        # Initialize MGXS Library for a few cross section types
+        self.mgxs_lib = openmc.mgxs.Library(self._input_set.geometry)
+        self.mgxs_lib.by_nuclide = False
+        self.mgxs_lib.mgxs_types = ['total', 'absorption', 'nu-fission matrix',
+                                    'nu-scatter matrix', 'multiplicity matrix']
+        self.mgxs_lib.energy_groups = energy_groups
+        self.mgxs_lib.correction = None
+        self.mgxs_lib.legendre_order = 3
+        self.mgxs_lib.domain_type = 'material'
+        self.mgxs_lib.build_library()
+
+        # Initialize a tallies file
+        self._input_set.tallies = openmc.Tallies()
+        self.mgxs_lib.add_to_tallies_file(self._input_set.tallies, merge=False)
+        self._input_set.tallies.export_to_xml()
+
+    def _run_openmc(self):
+        # Initial run
+        if self._opts.mpi_exec is not None:
+            returncode = openmc.run(mpi_procs=self._opts.mpi_np,
+                                    openmc_exec=self._opts.exe,
+                                    mpi_exec=self._opts.mpi_exec)
+
+        else:
+            returncode = openmc.run(openmc_exec=self._opts.exe)
+
+        assert returncode == 0, 'CE OpenMC calculation did not exit' \
+                                'successfully.'
+
+        # Build MG Inputs
+        # Get data needed to execute Library calculations.
+        statepoint = glob.glob(os.path.join(os.getcwd(), self._sp_name))[0]
+        sp = openmc.StatePoint(statepoint)
+        self.mgxs_lib.load_from_statepoint(sp)
+        self._input_set.mgxs_file, self._input_set.materials, \
+            self._input_set.geometry = self.mgxs_lib.create_mg_mode()
+
+        # Modify settings so we can run in MG mode
+        self._input_set.settings.cross_sections = './mgxs.xml'
+        self._input_set.settings.energy_mode = 'multi-group'
+
+        # Write modified input files
+        self._input_set.settings.export_to_xml()
+        self._input_set.geometry.export_to_xml()
+        self._input_set.materials.export_to_xml()
+        self._input_set.mgxs_file.export_to_xml()
+        # Dont need tallies.xml, so remove the file
+        if os.path.exists('./tallies.xml'):
+            os.remove('./tallies.xml')
+
+        # Re-run MG mode.
+        if self._opts.mpi_exec is not None:
+            returncode = openmc.run(mpi_procs=self._opts.mpi_np,
+                                    openmc_exec=self._opts.exe,
+                                    mpi_exec=self._opts.mpi_exec)
+
+        else:
+            returncode = openmc.run(openmc_exec=self._opts.exe)
+
+    def _cleanup(self):
+        super(MGXSTestHarness, self)._cleanup()
+        f = os.path.join(os.getcwd(), 'tallies.xml')
+        f = os.path.join(os.getcwd(), 'mgxs.xml')
+        if os.path.exists(f): os.remove(f)
+
+
+if __name__ == '__main__':
+    harness = MGXSTestHarness('statepoint.10.*', True)
+    harness.main()