typo fixes; fix tests; update msbr example

Author: yardasol

examples/msbr/msbr_endfb71_main.json

@@ -1,7 +1,7 @@
 {
    "proc_input_file": "msbr_objects.json",
    "dot_input_file": "msbr.dot",
-   "n_depletion_steps": 12,
+   "n_depletion_steps": 122,
    "output_path": "serpent_msbr_test",
    "depcode": {
        "codename": "serpent",

examples/msbr/msbr_openmc.json

@@ -0,0 +1,29 @@
+{
+   "proc_input_file": "msbr_objects.json",
+   "dot_input_file": "msbr.dot",
+   "n_depletion_steps": 122, 
+   "output_path": "openmc_msbr_test",
+   "depcode": {
+       "codename": "openmc",
+       "template_input_file_path": {
+           "materials": "materials.xml",
+           "settings": "settings.xml"},
+       "geo_file_paths": ["geometry.xml"],
+       "chain_file_path": "chain_endfb71_pwr.xml",
+       "depletion_settings": {
+           "operator_kwargs": {
+               "fission_q": "serpent_fissq.json"
+           }
+       }
+   },
+   "simulation": {
+       "sim_name": "msbr_openmc_test"
+   },
+   "reactor": {
+       "volume": 1.0,
+       "mass_flowrate": 9920000,
+       "power_levels": [ 2250000000 ],
+       "depletion_timesteps": [ 3 ],
+       "timestep_units": "d"
+   }
+}

saltproc/openmc_depcode.py

@@ -466,7 +466,7 @@ def write_runtime_input(self, reactor, depletion_step, restart):
         geometry.export_to_xml(self.runtime_inputfile['geometry'])
         settings.export_to_xml(self.runtime_inputfile['settings'])
         self.write_depletion_settings(reactor, depletion_step)
-        self.write_saltproc_openmc_tallies(materials, geometry, _ENERGY_BOUNDS, _N_DELAYED_GROUPS)
+        self.write_saltproc_openmc_tallies(materials, geometry, _DELAYED_ENERGY_BOUNDS, _N_DELAYED_GROUPS)
         del materials, geometry, settings
 
     def write_depletion_settings(self, reactor, step_idx):

tests/integration_tests/file_interface_openmc/test.py

@@ -8,6 +8,9 @@
 import pytest
 import openmc
 
+from saltproc.openmc_depcode import _DELAYED_ENERGY_BOUNDS, _N_DELAYED_GROUPS
+
+
 
 @pytest.fixture
 def setup(scope='module'):
@@ -109,7 +112,8 @@ def test_write_saltproc_openmc_tallies(setup, openmc_depcode):
         openmc_depcode.template_input_file_path['materials'])
     geo = openmc.Geometry.from_xml(
         openmc_depcode.geo_file_paths[0], mat)
-    openmc_depcode.write_saltproc_openmc_tallies(mat, geo)
+    openmc_depcode.write_saltproc_openmc_tallies(mat, geo,
+                                                 _DELAYED_ENERGY_BOUNDS, _N_DELAYED_GROUPS)
     del mat, geo
     tallies = openmc.Tallies.from_xml(openmc_depcode.runtime_inputfile['tallies'])
 
@@ -160,7 +164,8 @@ def test_read_neutronics_parameters(setup, openmc_depcode):
         openmc_depcode.template_input_file_path['materials'])
     geo = openmc.Geometry.from_xml(
         openmc_depcode.geo_file_paths[0], mat)
-    openmc_depcode.write_saltproc_openmc_tallies(mat, geo)
+    openmc_depcode.write_saltproc_openmc_tallies(mat, geo,
+                                                 _DELAYED_ENERGY_BOUNDS, _N_DELAYED_GROUPS)
 
     old_output_path = openmc_depcode.output_path
     openmc_depcode.output_path = Path(__file__).parents[2] / 'openmc_data/saltproc_runtime_ref'