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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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  pinspec | |
  log | Utility functions for writing log messages to the screen |
| plotter | The plotter module provides utility functions to plot data from PINSPEC's C++ classes, in particular, tally data and cross-sections, thermal scattering PDFs/CDFs, etc |
| process | The process module provides utility functions to retrieve data from PINSPEC's C++ classes, in particular, tally data |
 RIEff | An effective resonance integral |
| RITrue | A true resonance integral |
 GroupXS | A multi-group cross-section for a certain reaction rate |
| slbw | The slbw module provides utility functions to generate resonant cross-sections using the Single-Level Breit-Wigner formalism |
| BoundedFuelRegion | The BoundedFuelRegion is a circular fuel pin region bounded by the interior halfspace of a circle surface |
| BoundedGeneralRegion | The BoundedGeneralRegion is a the space defined by the intersection of some number surface halfspaces |
| BoundedModeratorRegion | The BoundedModeratorRegion is a the space defined four surfaces bounding a square pin minus a circular fuel pin region |
| BoundedRegion | The BoundedRegion is a region bounded by surfaces using a constructive solid geometry formulation |
| DerivedTally | A class for tallies resulting from tally arithmetic operations |
| EquivalenceFuelRegion | The EquivalenceFuelRegion is a fuel region treated using the heterogenous-homogeneous equivalence theory |
| EquivalenceModeratorRegion | The EquivalenceModeratorRegion is a fuel region treated using the heterogenous-homogeneous equivalence theory |
| EquivalenceRegion | The Equivalence Region is a fuel or moderator region treated using the heterogenous-homogeneous equivalence theory |
| Fissioner | The Fissioner represents the physics of fission neutron emission |
| Geometry | The Geometry represents the highest level entity in which a neutron may reside during a PINSPEC simulaiton. The geometry consists of one or more regions and controls the highest level Monte Carlo kernel |
| GeometryAbsorptionRateTally | A class for tallying the absorption within the geometry |
| GeometryCaptureRateTally | A class for tallying the capture rate within the geometry |
| GeometryCollisionRateTally | A class for tallying the collision rate within the geometry |
| GeometryDiffusionRateTally | A class for tallying the capture rate for an isotope |
| GeometryElasticRateTally | A class for tallying the elastic scattering rate within the geometry |
| GeometryFissionRateTally | A class for tallying the capture rate for an isotope |
| GeometryFluxTally | A class for tallying the flux for the geometry |
| GeometryGroupRateTally | A class for tallying the group-to-group scattering rate within the geometry |
| GeometryInterCollisionTimeTally | A class for tallying the time between collisions for the geometry |
| GeometryLeakageRateTally | A class for tallying the leakage rate for the geometry |
| GeometryOutScatterRateTally | A class for tallying the outter scattering rate within the geometry |
| GeometryTally | An abstract class for tallies with MATERIAL domain type |
| GeometryTransportRateTally | A class for tallying the transport rate within the geometry |
| InfiniteMediumRegion | The InfiniteMediumRegion is a homogenized region treated without geometric effects |
| Isotope | The Isotope represents a nuclide at some temperature |
| IsotopeAbsorptionRateTally | A class for tallying the absorption rate for an isotope |
| IsotopeCaptureRateTally | A class for tallying the capture rate for an isotope |
| IsotopeCollisionRateTally | A class for tallying the collision rate for an isotope |
| IsotopeDiffusionRateTally | A class for tallying the diffusion rate for an isotope |
| IsotopeElasticRateTally | A class for tallying the elastic scattering rate for an isotope |
| IsotopeFissionRateTally | A class for tallying the fission rate for an isotope |
| IsotopeGroupRateTally | A class for tallying the group-to-group scattering rate for an isotope |
| IsotopeOutScatterRateTally | A class for tallying the outter scattering rate for an isotope |
| IsotopeTally | An abstract class for tallies with ISOTOPE domain type |
| IsotopeTransportRateTally | A class for tallying the transport rate for an isotope |
| Material | Collection of isotope objects |
| MaterialAbsorptionRateTally | A class for tallying the absorption rate within a material |
| MaterialCaptureRateTally | A class for tallying the collision rate within a material |
| MaterialCollisionRateTally | A class for tallying the collision rate within a material |
| MaterialDiffusionRateTally | A class for tallying the diffusion rate within a material |
| MaterialElasticRateTally | A class for tallying the elastic scattering rate within a material |
| MaterialFissionRateTally | A class for tallying the capture rate within a material |
| MaterialFluxTally | A class for tallying the flux in all regions filled by a material |
| MaterialGroupRateTally | A class for tallying the group-to-group scattering rate within a material |
| MaterialInterCollisionTimeTally | A class for tallying the time between collision with a material |
| MaterialLeakageRateTally | A class for tallying the leakage rate for the regions filled by a material |
| MaterialOutScatterRateTally | A class for tallying the out scattering rate within a material |
| MaterialTally | An abstract class for tallies with MATERIAL domain type |
| MaterialTransportRateTally | A class for tallying the transport rate within a material |
| neutron | Represents a neutron in a PINSPEC simulation |
| Region | The region class represents a region in 2D space |
| RegionAbsorptionRateTally | A class for tallying the absorption rate within a region |
| RegionCaptureRateTally | A class for tallying the capture rate within a region |
| RegionCollisionRateTally | A class for tallying the collision rate within a region |
| RegionDiffusionRateTally | A class for tallying the diffusion rate within a region |
| RegionElasticRateTally | A class for tallying the elastic scattering rate within a region |
| RegionFissionRateTally | A class for tallying the fission rate within a region. |
| RegionFluxTally | A class for tallying the flux for a region |
| RegionGroupRateTally | A class for tallying the group-to-group scattering rate within a region |
| RegionInterCollisionTimeTally | A class for tallying the time between collisions for the region |
| RegionLeakageRateTally | A class for tallying the leakage rate for a region |
| RegionOutScatterRateTally | A class for tallying the outter scattering rate within a region |
| RegionTally | An abstract class for tallies with REGION domain type |
| RegionTransportRateTally | A class for tallying the transport rate within a region |
| Surface | The Surface represents a quadratic surface in the xy-plane |
| Tally | A Tally reprsents a set of bins for tallying some quantity |
| TallyBank | The TallyBank contains all tallies for a simulation |
| TallyFactory | A utility class for creating instances of tallies |
| Timer | The Timer represents a simulation stopwatch |
| XPlane | The XPlane is a plane perpendicular to the y-axis |
| YPlane | The YPlane is a a plane perpendicular to the y-axis |
| ZCylinder | The ZCylinder is the locus of a point equidistant from a fixed point |
1.8.6 
