From a62dc7868f26ffcbcc8fc78129ec760257c6bc15 Mon Sep 17 00:00:00 2001 From: "wbinventor@gmail.com" Date: Tue, 2 Feb 2016 15:53:27 -0500 Subject: [PATCH] Added test for distribcell tallies in an asymmetric lattice --- tests/test_asymmetric_lattice/inputs_true.dat | 1 + .../test_asymmetric_lattice/results_true.dat | 1 + .../test_asymmetric_lattice.py | 127 ++++++++++++++++++ 3 files changed, 129 insertions(+) create mode 100644 tests/test_asymmetric_lattice/inputs_true.dat create mode 100644 tests/test_asymmetric_lattice/results_true.dat create mode 100644 tests/test_asymmetric_lattice/test_asymmetric_lattice.py diff --git a/tests/test_asymmetric_lattice/inputs_true.dat b/tests/test_asymmetric_lattice/inputs_true.dat new file mode 100644 index 0000000000..70073c6bd2 --- /dev/null +++ b/tests/test_asymmetric_lattice/inputs_true.dat @@ -0,0 +1 @@ +dd39c0ae6327e6e74cb077d56e37c112611b95c4c10d96203e672b3e7f928211cc991ec7ebbf9eeadabd968dcdcb651b250233169b62d43ef6994ab9a46cb34a \ No newline at end of file diff --git a/tests/test_asymmetric_lattice/results_true.dat b/tests/test_asymmetric_lattice/results_true.dat new file mode 100644 index 0000000000..d809e6409d --- /dev/null +++ b/tests/test_asymmetric_lattice/results_true.dat @@ -0,0 +1 @@ +7e75ad5b7979e65e52ce564bfbd8fac819013ef8ba35fe184569b452dd9a1ba98d267b6e33d357fdd1c943f201125ff8a4f8601147b87036525870528063dcae \ No newline at end of file diff --git a/tests/test_asymmetric_lattice/test_asymmetric_lattice.py b/tests/test_asymmetric_lattice/test_asymmetric_lattice.py new file mode 100644 index 0000000000..7b83a590ef --- /dev/null +++ b/tests/test_asymmetric_lattice/test_asymmetric_lattice.py @@ -0,0 +1,127 @@ +#!/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 +from openmc.source import Source +from openmc.stats import Box + + +class AsymmetricLatticeTestHarness(PyAPITestHarness): + + def _build_inputs(self): + """Build an axis-asymmetric lattice of fuel assemblies""" + + # Build full core geometry from underlying input set + self._input_set.build_default_materials_and_geometry() + + # Extract all universes from the full core geometry + geometry = self._input_set.geometry.geometry + all_univs = geometry.get_all_universes() + print(all_univs.keys()) + + # Extract universes encapsulating fuel and water assemblies + water = all_univs[7] + fuel = all_univs[8] + + # Construct a 3x3 lattice of fuel assemblies + core_lat = openmc.RectLattice(name='3x3 Core Lattice', lattice_id=202) + core_lat.dimension = (3, 3) + core_lat.lower_left = (-32.13, -32.13) + core_lat.pitch = (21.42, 21.42) + core_lat.universes = [[fuel, water, water], + [fuel, fuel, fuel], + [water, water, water]] + + # Create bounding surfaces + min_x = openmc.XPlane(x0=-32.13, boundary_type='reflective') + max_x = openmc.XPlane(x0=+32.13, boundary_type='reflective') + min_y = openmc.YPlane(y0=-32.13, boundary_type='reflective') + max_y = openmc.YPlane(y0=+32.13, boundary_type='reflective') + min_z = openmc.ZPlane(z0=0, boundary_type='reflective') + max_z = openmc.ZPlane(z0=+32.13, boundary_type='reflective') + + # Define root universe + root_univ = openmc.Universe(universe_id=0, name='root universe') + root_cell = openmc.Cell(cell_id=1) + root_cell.region = +min_x & -max_x & +min_y & -max_y & +min_z & -max_z + root_cell.fill = core_lat + root_univ.add_cell(root_cell) + + # Over-ride geometry in the input set with this 3x3 lattice + self._input_set.geometry.geometry.root_universe = root_univ + + # Initialize a "distribcell" filter for the cold fuel pin cell + distrib_filter = openmc.Filter(type='distribcell', bins=[27]) + + # Initialize the tallies + tally = openmc.Tally(name='distribcell tally', tally_id=27) + tally.add_filter(distrib_filter) + tally.add_score('nu-fission') + + # Initialize the tallies file + tallies_file = openmc.TalliesFile() + tallies_file.add_tally(tally) + + # Assign the tallies file to the input set + self._input_set.tallies = tallies_file + + # Specify summary output and correct source sampling box + self._input_set.build_default_settings() + self._input_set.settings.output = {'summary': True} + self._input_set.settings.source = Source(space=Box( + [0, 0, 0], [32.13, 32.13, 32.13])) + + # Write input XML files + self._input_set.export() + + def _get_results(self, hash_output=True): + """Digest info in statepoint and summary and return as a string.""" + + # Read the statepoint file + statepoint = glob.glob(os.path.join(os.getcwd(), self._sp_name))[0] + sp = openmc.StatePoint(statepoint) + + # Read the summary file + summary = glob.glob(os.path.join(os.getcwd(), 'summary.h5'))[0] + su = openmc.Summary(summary) + sp.link_with_summary(su) + + # Extract the tally of interest + tally = sp.get_tally(name='distribcell tally') + + # Create a string of all mean, std. dev. values for both tallies + outstr = '' + outstr += ', '.join(map(str, tally.mean.flatten())) + '\n' + outstr += ', '.join(map(str, tally.std_dev.flatten())) + '\n' + + # Extract fuel assembly lattices from the summary + all_cells = su.openmc_geometry.get_all_cells() + fuel = all_cells[80].fill + core = all_cells[1].fill + + # Append a string of lattice distribcell offsets to the string + outstr += ', '.join(map(str, fuel.offsets.flatten())) + '\n' + outstr += ', '.join(map(str, core.offsets.flatten())) + '\n' + + # Hash the results if necessary + if hash_output: + sha512 = hashlib.sha512() + sha512.update(outstr.encode('utf-8')) + outstr = sha512.hexdigest() + + return outstr + + def _cleanup(self): + super(AsymmetricLatticeTestHarness, self)._cleanup() + f = os.path.join(os.getcwd(), 'tallies.xml') + if os.path.exists(f): os.remove(f) + + +if __name__ == '__main__': + harness = AsymmetricLatticeTestHarness('statepoint.10.h5', True) + harness.main()