diff --git a/docs/source/pythonapi/examples/mgxs-part-i.ipynb b/docs/source/pythonapi/examples/mgxs-part-i.ipynb index 7b20a97db..e7b8cc73a 100644 --- a/docs/source/pythonapi/examples/mgxs-part-i.ipynb +++ b/docs/source/pythonapi/examples/mgxs-part-i.ipynb @@ -433,7 +433,7 @@ " \tName =\t\n", " \tFilters =\t\n", " \t\tmesh\t[10000]\n", - " \t\tenergy\t[0.000000E+00 6.250000E-07 2.000000E+01]\n", + " \t\tenergy\t[ 0.00000000e+00 6.25000000e-07 2.00000000e+01]\n", " \tNuclides =\ttotal \n", " \tScores =\t['flux']\n", " \tEstimator =\ttracklength), ('absorption', Tally\n", @@ -441,7 +441,7 @@ " \tName =\t\n", " \tFilters =\t\n", " \t\tmesh\t[10000]\n", - " \t\tenergy\t[0.000000E+00 6.250000E-07 2.000000E+01]\n", + " \t\tenergy\t[ 0.00000000e+00 6.25000000e-07 2.00000000e+01]\n", " \tNuclides =\ttotal \n", " \tScores =\t['absorption']\n", " \tEstimator =\ttracklength)])" @@ -520,9 +520,10 @@ "\n", " Copyright: 2011-2016 Massachusetts Institute of Technology\n", " License: http://openmc.readthedocs.io/en/latest/license.html\n", - " Version: 0.7.1\n", - " Git SHA1: 3d68c07625e33cd64188df03ee03e9c31b3d4b74\n", - " Date/Time: 2016-07-22 21:03:18\n", + " Version: 0.8.0\n", + " Git SHA1: 16e74656b028875a7ebcb90df07293c5f1cc56a4\n", + " Date/Time: 2016-07-29 13:20:18\n", + " MPI Processes: 1\n", "\n", " ===========================================================================\n", " ========================> INITIALIZATION <=========================\n", @@ -532,11 +533,11 @@ " Reading geometry XML file...\n", " Reading cross sections XML file...\n", " Reading materials XML file...\n", - " Reading H1.71c from /home/romano/openmc/data/nndc_hdf5/H1_71c.h5\n", - " Reading O16.71c from /home/romano/openmc/data/nndc_hdf5/O16_71c.h5\n", - " Reading U235.71c from /home/romano/openmc/data/nndc_hdf5/U235_71c.h5\n", - " Reading U238.71c from /home/romano/openmc/data/nndc_hdf5/U238_71c.h5\n", - " Reading Zr90.71c from /home/romano/openmc/data/nndc_hdf5/Zr90_71c.h5\n", + " Reading H1.71c from /Users/sam/git/openmc-sam/data/nndc_hdf5/H1_71c.h5\n", + " Reading O16.71c from /Users/sam/git/openmc-sam/data/nndc_hdf5/O16_71c.h5\n", + " Reading U235.71c from /Users/sam/git/openmc-sam/data/nndc_hdf5/U235_71c.h5\n", + " Reading U238.71c from /Users/sam/git/openmc-sam/data/nndc_hdf5/U238_71c.h5\n", + " Reading Zr90.71c from /Users/sam/git/openmc-sam/data/nndc_hdf5/Zr90_71c.h5\n", " Maximum neutron transport energy: 20.0000 MeV for H1.71c\n", " Reading tallies XML file...\n", " Building neighboring cells lists for each surface...\n", @@ -607,20 +608,20 @@ "\n", " =======================> TIMING STATISTICS <=======================\n", "\n", - " Total time for initialization = 3.2300E-01 seconds\n", - " Reading cross sections = 1.6900E-01 seconds\n", - " Total time in simulation = 1.9882E+01 seconds\n", - " Time in transport only = 1.9869E+01 seconds\n", - " Time in inactive batches = 2.6590E+00 seconds\n", - " Time in active batches = 1.7223E+01 seconds\n", - " Time synchronizing fission bank = 4.0000E-03 seconds\n", - " Sampling source sites = 4.0000E-03 seconds\n", - " SEND/RECV source sites = 0.0000E+00 seconds\n", + " Total time for initialization = 3.8300E-01 seconds\n", + " Reading cross sections = 2.0900E-01 seconds\n", + " Total time in simulation = 2.3245E+01 seconds\n", + " Time in transport only = 2.3223E+01 seconds\n", + " Time in inactive batches = 2.0320E+00 seconds\n", + " Time in active batches = 2.1213E+01 seconds\n", + " Time synchronizing fission bank = 1.0000E-02 seconds\n", + " Sampling source sites = 7.0000E-03 seconds\n", + " SEND/RECV source sites = 2.0000E-03 seconds\n", " Time accumulating tallies = 0.0000E+00 seconds\n", - " Total time for finalization = 0.0000E+00 seconds\n", - " Total time elapsed = 2.0217E+01 seconds\n", - " Calculation Rate (inactive) = 9402.03 neutrons/second\n", - " Calculation Rate (active) = 5806.19 neutrons/second\n", + " Total time for finalization = 1.0000E-03 seconds\n", + " Total time elapsed = 2.3642E+01 seconds\n", + " Calculation Rate (inactive) = 12303.1 neutrons/second\n", + " Calculation Rate (active) = 4714.09 neutrons/second\n", "\n", " ============================> RESULTS <============================\n", "\n", diff --git a/openmc/mgxs/mgxs.py b/openmc/mgxs/mgxs.py index 539904744..1ef3194be 100644 --- a/openmc/mgxs/mgxs.py +++ b/openmc/mgxs/mgxs.py @@ -773,6 +773,13 @@ class MGXS(object): cv.check_value('value', value, ['mean', 'std_dev', 'rel_err']) cv.check_value('xs_type', xs_type, ['macro', 'micro']) + # FIXME: Unable to get microscopic xs for mesh domain because the mesh + # cells do not know the nuclide densities in each mesh cell. + if self.domain_type == 'mesh' and xs_type == 'micro': + msg = 'Unable to get micro xs for mesh domain since the mesh ' \ + 'cells do not know the nuclide densities in each mesh cell.' + raise ValueError(msg) + filters = [] filter_bins = []