MURE
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Class Hierarchy
This inheritance list is sorted roughly, but not completely, alphabetically:
[detail level 1234]
oCAlphaNTabsAlphaNTabs contains
oCBasePriorityDefine priorites of nuclear databases to choose nuclei from BaseSummary.dat file
oCBetaCollectorDefine Beta collector for anti-neutrinos studies
oCBetaSpectraDefine Beta spectra and reaction for anti-neutrinos studies
oCCellA Cell is a MCNP cell
oCCellHeaderHeader of an evolving cell in a binary file
oCCellOccupyThis class holds a list of all positions in the core lattice occupied by one cell (one universe number)
oCDynamicalSystemDynamicalSystem class solves system of differential equations
|\CEvolutiveSystemEvolutiveSystem class carries out evolution
oCEqualReactionComparison operator for Reaction class
oCEvolutionControlEvolutionControl allows interactions with the evolution
|oCEvolutionWrapperFront-end class for Evolution(): enables easy and comprehensive specification of operation history, as well as core reshuffling
|oCFissileEvolutionControlEvolution control for Fissile content
|oCHNEvolutionControlEvolutionControl for heavy nuclide content control
|oCInLineReprocessingInLineReprocessing is an EvolutionControl class for reprocessing without moving material
|oCPoisonEvolutionControlEvolutionControl descendant for controlling evolution via absorption of control (poison) material
|\CRodEvolutionControlEvolutionControl descendant allowing control via control rod insertion
oCExternalFuelA ExternalFuel do what????????
oCFileHeaderHeader of MURE output binary file
oCFissionProductA FissionProduct Nucleus
oCFPDistributionA "vector" of FPDistribution
oCFPRecordA record in the data file where Fission Product are define
oCFuelReprocessingFuelReprocessing allows Fuel reprocessing during Evolution
|\CBlanketReprocessingBlanketReprocessing allows Fuel reprocessing in Core and in Blanket during Evolution
oCMaterialA Material constituing a Cell
|\CControlMaterialA ControlMaterial
oCMatXStructure holding Material and a number (e.g. density, temperature etc.)
oCMCNPSourceDefine a MCNP Source
oCMeshTallyDefine a MeshTally class (abstract)
|oCFMeshTallyDefine a MCNPX TMeshTally
|\CTMeshTallyDefine a MCNPX TMeshTally
oCMUREMURE class allow to make connections between classes
oCNuclearChartA NuclearChart is a 2 dimensional array of nuclei up to maximum N & Z
oCNucleiTreeA NucleiTree defines the whole tree of nuclei in case of evolution for a single ZAI
oCNucleusRecordRecord of a nucleus in a binary file
oCReactionDefine a Reaction list for Tally multiplicator inputs
oCReactionListReactions to take into account for evolution of a given nucleus
oCReactionRecordRecord of a reaction in a binary file
oCReactorChannelThis is a MURE compound or multi-cellular object
oCReactorMeshManages filled assembly geometry - can be used for a coupled analysis with thermal hydraulics (cf. Class COBRA)
|\CCOBRAManages the coupling analysis with thermal hydraulics code COBRA-EN
oCReadXSFileAllows to read XS file in the MCNP ACE format
oCReference_ptr< T >Handle dynamical object creation and pointer affectation
oCReference_ptr< Shape >
oCReshufflingSchemeThis class performs reshuffling of a lattice
oCSpecialIsomerClass to define special treatment for some isomers
oCSpectrumBase class to define spectra
|oCAlphaSpectrumAlphaSpectrum contains a histogram of Alpha ray intensities
|oCBetaSpectrumBetaSpectrum contains a histogram of Beta ray intensities
|oCGammaSpectrumGammaSpectrum defines of gamma ray spectrum
|\CNeutronSpectrumNeutronSpectrum contains a histogram of Neutron intensities
oCStorageStorage are outcore containers
oCStoredXSforZAIStoredXSforZAI is a class for storing some XS and use them later in the cycle
oCStringLineClass extracting fields from a string / line
|\CXSDIRLineExtract all parameters from an XSDIR line
oCSurfaceSurface class is design to define MCNP surface format
oCTallyDefine a MCNP Tally
oCTallyBinDefine a general MCNP Tally Bin (cell or surface)
|oCGroupBinDefine group a cell or surface bin
|oCLatticeBinDefine Lattice Cell type bin
|\CSimpleBinDefine a Simple Bin
oCTallyFMDefine a Tally Multiplicator entry (FM card in MCNP)
oCTempCoefCalculatorThis object performs temperature coefficient calculations for a general system
oCTemperatureMapThe good way of handling temperature from data base
oCTemporalStorageTemporalStorage are outcore containers function of a Retreatment time
oCTFunctorAbstract class to define Functor (function of function)
|\CTSpecificFunctor< T >Template class to assign a method of class T as argument
oCThermalCouplingThis object performs the variation of temperature in a given region for a specific system
oCThermalDataReaderThis object reads thermodynamics values of fluids that are stored in files stored in MURE/thermal_data/
oCTransformationSpatial Transformation for TR & TRCL cards
oCTReferenceBase class to reference all Shape objects
|oCNucleusA real Nucleus with a Temperature
|\CShapeBase class to define shapes
| oCBrickA rectangular parallepipede Shape
| oCCylinderInfinite cylinder Shape
| oCNodeNode allows to construct Union or Intersection of Shape
| |oCHexagonRegular hexagon Shape of a given height
| |\CTubeA Tube is a finite Cylinder with a hole inside (like a pipe)
| oCPlaneInfinite plane Shape
| \CSphereDefine a Sphere Shape
oCVoidCoefCalculatorVoid coefficient calculations for a general system
oCXSDIRHandle XSDIR file in order to extract information that could be easily retreived
oCZAIA ZAI defined a (Z,A,Isomere) for a Nucleus
oCZAIReactionA very simple class which contains the Reaction code and its weight for possible nuclear reactions of a ZAI
\CT

MURE Project, documentation generated by Doxygen 1.8.5 - Mon Nov 17 2014