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A monte carlo pin cell spectral code for nuclear engineering applications.
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A monte carlo pin cell spectral code for nuclear engineering applications.
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The InfiniteMediumRegion is a homogenized region treated without geometric effects. More...
#include "pinspec/src/Region.h"
Public Member Functions | |
| InfiniteMediumRegion (const char *region_name=(char *)"") | |
| InfiniteMediumRegion constructor. More... | |
| virtual | ~InfiniteMediumRegion () |
| Empty destructor allows SWIG to cleanup memory for surfaces. | |
| void | collideNeutron (neutron *neutron) |
| This method collides a neutron within the region. More... | |
 Public Member Functions inherited from Region | |
| Region (const char *region_name=(char *)"") | |
| Region constructor. More... | |
| virtual | ~Region () |
| Empty destructor allows SWIG to cleanup memory for surfaces. More... | |
| char * | getName () |
| Return the name of the region. More... | |
| int | getUid () const |
| Returns the unique ID auto-generated for the region. More... | |
| Material * | getMaterial () |
| Returns a pointer to the material filling this region. More... | |
| bool | containsIsotope (Isotope *isotope) |
| Determines whether this region contains a particular isotope. More... | |
| regionType | getRegionType () |
| Return the type of region. More... | |
| float | getVolume () |
returns the volume of this Region  . More... | |
| float | getBucklingSquared () |
| Returns the squared geometric buckling. More... | |
| float | getTotalMacroXS (float energy) |
| Computes and returns the total macroscopic cross-section in the region at some energy (eV). More... | |
| float | getTotalMacroXS (int energy_index) |
| Computes and returns the total macroscopic cross-section in the region at some index into the uniform lethargy grid. More... | |
| float | getTotalMicroXS (float energy) |
| Computes and returns the total microscopic cross-section in the region at some energy (eV). More... | |
| float | getTotalMicroXS (int energy_index) |
| Computes and returns the total microscopic cross-section in the region at some index into the uniform lethargy grid. More... | |
| float | getElasticMacroXS (float energy) |
| Computes and returns the macroscopic elastic scattering cross-section in the region at some energy (eV). More... | |
| float | getElasticMacroXS (int energy_index) |
| Computes and returns the macroscopic elastic scattering cross-section in the region at some index into the uniform lethargy grid. More... | |
| float | getElasticMicroXS (float energy) |
| Computes and returns the microscopic elastic scattering cross-section in the region at some energy (eV). More... | |
| float | getElasticMicroXS (int energy_index) |
| Computes and returns the microscopic elastic scattering cross-section in the region at some index into the uniform lethargy grid. More... | |
| float | getAbsorptionMacroXS (float energy) |
| Computes and returns the macroscopic absorption cross-section in the region at energy (eV). More... | |
| float | getAbsorptionMacroXS (int energy_index) |
| Computes and returns the macroscopic absorption cross-section in the region at some index into the uniform lethargy grid. More... | |
| float | getAbsorptionMicroXS (float energy) |
| Computes and returns the microscopic absorption cross-section in the region at some energy (eV). More... | |
| float | getAbsorptionMicroXS (int energy_index) |
| Computes and returns the microscopic absorption cross-section in the region at some index into the uniform lethargy grid. More... | |
| float | getCaptureMacroXS (float energy) |
| Computes and returns the macroscopic capture cross-section in the region at some energy (eV). More... | |
| float | getCaptureMacroXS (int energy_index) |
| Computes and returns the macroscopic capture cross-section in the region at some index into the uniform lethargy grid. More... | |
| float | getCaptureMicroXS (float energy) |
| Computes and returns the microscopic capture cross-section in the region at some energy (eV). More... | |
| float | getCaptureMicroXS (int energy_index) |
| Computes and returns the microscopic capture cross-section in the region at some index into the uniform lethargy grid. More... | |
| float | getFissionMacroXS (float energy) |
| Computes and returns the macroscopic fission cross-section in the region at some energy (eV). More... | |
| float | getFissionMacroXS (int energy_index) |
| Computes and returns the macroscopic fission cross-section in the region at some index into the uniform lethargy grid. More... | |
| float | getFissionMicroXS (float energy) |
| Computes and returns the microscopic fission cross-section in the region at some energy (eV) More... | |
| float | getFissionMicroXS (int energy_index) |
| Computes and returns the microscopic fission cross-section in the region at some index into the uniform lethargy grid. More... | |
| float | getTransportMicroXS (float energy) |
| Computes and returns the microscopic transport cross-section in the region at some index into the uniform lethargy grid. More... | |
| float | getTransportMicroXS (int energy_index) |
| Computes and returns the microscopic transport cross-section in the region at some index into the uniform lethargy grid. More... | |
| float | getTransportMacroXS (float energy) |
| Computes and returns the macroscopic transport cross-section in the region at some index into the uniform lethargy grid. More... | |
| float | getTransportMacroXS (int energy_index) |
| Computes and returns the macroscopic transport cross-section in the region at some index into the uniform lethargy grid. More... | |
| void | setMaterial (Material *material) |
| Set the material filling this region. More... | |
| void | setVolume (float volume) |
| Sets the volume for this region . More... | |
| void | setBucklingSquared (float buckling_squared) |
| Sets the squared geometric buckling for the geometry. More... | |
Additional Inherited Members | |
| Protected Attributes inherited from Region | |
| char * | _region_name |
| int | _uid |
| Material * | _material |
| regionType | _region_type |
| float | _buckling_squared |
| float | _volume |
| Static Protected Attributes inherited from Region | |
| static int | _n = 1 |
The InfiniteMediumRegion is a homogenized region treated without geometric effects.
Only a single InfiniteMedium Region should be defined for a given PINSPEC simulation. An infinite medium spectral calculation in in PINSPEC neglects the location of particles and only treats neutron elastic and thermal capture, scattering and fission events.
| InfiniteMediumRegion::InfiniteMediumRegion | ( | const char * | region_name = (char*)"" | ) |
InfiniteMediumRegion constructor.
Sets defaults for the geometric parameters to 0.
| region_name | the name of the region |
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virtual |
This method collides a neutron within the region.
This method encapsulates all of the neutron scattering physics which is further encapsulated by the material and isotope classes.
| neutron | the neutron of interest |
Implements Region.
1.8.6 
