| /dports/science/py-OpenMC/openmc-0.12.2/tests/unit_tests/ |
| H A D | test_settings.py | 53 s.create_fission_neutrons = True
110 assert s.create_fission_neutrons
|
| /dports/science/openmc/openmc-0.12.2/tests/unit_tests/ |
| H A D | test_settings.py | 53 s.create_fission_neutrons = True
110 assert s.create_fission_neutrons
|
| /dports/science/py-OpenMC/openmc-0.12.2/include/openmc/ |
| H A D | settings.h | 30 extern bool create_fission_neutrons; //!< create fission neutrons (fixed source)?
|
| /dports/science/openmc/openmc-0.12.2/include/openmc/ |
| H A D | settings.h | 30 extern bool create_fission_neutrons; //!< create fission neutrons (fixed source)?
|
| /dports/science/py-OpenMC/openmc-0.12.2/tests/regression_tests/create_fission_neutrons/ |
| H A D | test.py | 38 settings_file.create_fission_neutrons = False
|
| /dports/science/openmc/openmc-0.12.2/tests/regression_tests/create_fission_neutrons/ |
| H A D | test.py | 38 settings_file.create_fission_neutrons = False
|
| /dports/science/py-OpenMC/openmc-0.12.2/openmc/ |
| H A D | settings.py | 422 def create_fission_neutrons(self): member in Settings
806 @create_fission_neutrons.setter
807 def create_fission_neutrons(self, create_fission_neutrons): member in Settings
809 create_fission_neutrons, bool)
810 self._create_fission_neutrons = create_fission_neutrons
1383 self.create_fission_neutrons = text in ('true', '1')
|
| /dports/science/openmc/openmc-0.12.2/openmc/ |
| H A D | settings.py | 422 def create_fission_neutrons(self): member in Settings
806 @create_fission_neutrons.setter
807 def create_fission_neutrons(self, create_fission_neutrons): member in Settings
809 create_fission_neutrons, bool)
810 self._create_fission_neutrons = create_fission_neutrons
1383 self.create_fission_neutrons = text in ('true', '1')
|
| /dports/science/py-OpenMC/openmc-0.12.2/src/ |
| H A D | finalize.cpp | 75 settings::create_fission_neutrons = true; in openmc_finalize()
|
| H A D | physics_mg.cpp | 51 settings::create_fission_neutrons)) { in sample_reaction()
|
| H A D | settings.cpp | 45 bool create_fission_neutrons {true}; variable
811 create_fission_neutrons = get_node_value_bool(root, "create_fission_neutrons"); in read_settings_xml()
|
| H A D | physics.cpp | 106 settings::create_fission_neutrons) { in sample_neutron_reaction()
|
| /dports/science/openmc/openmc-0.12.2/src/ |
| H A D | finalize.cpp | 75 settings::create_fission_neutrons = true; in openmc_finalize()
|
| H A D | physics_mg.cpp | 51 settings::create_fission_neutrons)) { in sample_reaction()
|
| H A D | settings.cpp | 45 bool create_fission_neutrons {true}; variable
811 create_fission_neutrons = get_node_value_bool(root, "create_fission_neutrons"); in read_settings_xml()
|
| H A D | physics.cpp | 106 settings::create_fission_neutrons) { in sample_neutron_reaction()
|
| /dports/science/py-OpenMC/openmc-0.12.2/src/relaxng/ |
| H A D | settings.rnc | 6 element create_fission_neutrons { xsd:boolean }? &
|
| /dports/science/openmc/openmc-0.12.2/src/relaxng/ |
| H A D | settings.rnc | 6 element create_fission_neutrons { xsd:boolean }? &
|
| /dports/science/py-OpenMC/openmc-0.12.2/docs/source/io_formats/ |
| H A D | settings.rst | 36 ``<create_fission_neutrons>`` Element
39 The ``<create_fission_neutrons>`` element indicates whether fission neutrons
|
| /dports/science/openmc/openmc-0.12.2/docs/source/io_formats/ |
| H A D | settings.rst | 36 ``<create_fission_neutrons>`` Element
39 The ``<create_fission_neutrons>`` element indicates whether fission neutrons
|