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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 EquivalenceModeratorRegion is a fuel region treated using the heterogenous-homogeneous equivalence theory. More...
#include "pinspec/src/Region.h"
Public Member Functions | |
| EquivalenceModeratorRegion (const char *region_name=(char *)"") | |
| EquivalenceModeratorRegion constructor. More... | |
| ~EquivalenceModeratorRegion () | |
| Empty destructor allows SWIG to cleanup memory for surfaces. | |
 Public Member Functions inherited from EquivalenceRegion | |
| EquivalenceRegion (const char *region_name=(char *)"") | |
| EquivalenceRegion constructor. More... | |
| virtual | ~EquivalenceRegion () |
| Empty destructor allows SWIG to cleanup memory for surfaces. | |
| float | getFuelPinRadius () |
| Returns the fuel pin radius. More... | |
| float | getPinCellPitch () |
| Returns the pin cell pitch. More... | |
| int | getEnergyGridIndex (float lethargy) |
| This method returns the index for a certain lethargy (log10(eV)) into the uniform lethargy grid of the region's first flight collision probabilies. More... | |
| bool | isFuel () |
| Returns true if this region is the fuel, false otherwise. More... | |
| bool | isModerator () |
| Returns true if this region is the moderator, false otherwise. More... | |
| void | setFirstFlightCollProb (float *prob_ff, float *prob_mf, float *prob_energies, int num_prob) |
| Sets the first flight collision probabilities. More... | |
| void | setOtherRegion (EquivalenceRegion *region) |
| Sets other region for a homogeneous equivalence region. More... | |
| void | setFuelPinRadius (float radius) |
| Sets the fuel radius if the region. More... | |
| void | setPinCellPitch (float pitch) |
| Sets the pin cell pitch. More... | |
| float | computeFuelFuelCollsionProb (neutron *neutron) |
| Finds the first flight fuel-to-fuel collision probability for a neutron. More... | |
| float | computeModeratorFuelCollisionProb (neutron *neutron) |
| Finds the first flight moderator-to-fuel collision probability for a neutron. More... | |
| 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 EquivalenceModeratorRegion is a fuel region treated using the heterogenous-homogeneous equivalence theory.
In particular, this class uses Carlvik's Rational Approximation for first flight collision probabilities. This heterogeneous - homogeneous approximation allows this class to treat a heterogeneous pin cell simply as a homogeneous fuel and homogeneous moderator regions with probabilities for a particle to travel from one region to another at a given energy. This avoids the need for explicit ray tracing of particle trajectories across the geometry.
| EquivalenceModeratorRegion::EquivalenceModeratorRegion | ( | const char * | region_name = (char*)"" | ) |
EquivalenceModeratorRegion constructor.
| region_name | the name of the region |
1.8.6 
