A monte carlo pin cell spectral code for nuclear engineering applications.
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Here is a list of all documented class members with links to the class documentation for each member:
- s -
sampleCollisionType() :
Isotope
sampleDistanceTraveled() :
Material
sampleIsotope() :
Material
setA() :
Isotope
setAtomicMass() :
Material
setBatchMu() :
DerivedTally
setBatchRelErr() :
DerivedTally
setBatchStdDev() :
DerivedTally
setBatchVariance() :
DerivedTally
setBinEdges() :
Tally
setBinSpacingType() :
Tally
setBoundaryType() :
Surface
setBucklingSquared() :
Geometry
,
Material
,
Region
setCaptureXS() :
Isotope
setComputedBatchStatistics() :
DerivedTally
setDancoffFactor() :
Geometry
setDensity() :
Material
setElasticXS() :
Isotope
setEMax() :
Fissioner
setFirstFlightCollProb() :
EquivalenceRegion
setFissionXS() :
Isotope
setFuelPinRadius() :
EquivalenceRegion
,
Geometry
setGroupExpandBins() :
Tally
setMaterial() :
Region
setMaterialName() :
Material
setMultigroupCaptureXS() :
Isotope
setMultigroupElasticXS() :
Isotope
setMultigroupFissionXS() :
Isotope
setName() :
Geometry
,
pinspec.process.GroupXS
,
pinspec.process.RIEff
,
pinspec.process.RITrue
setNeutronsPerBatch() :
Geometry
setNumBatches() :
Geometry
,
Tally
setNumberDensity() :
Material
setNumBins() :
Fissioner
setNumThreads() :
Geometry
setOtherRegion() :
EquivalenceRegion
setPinCellPitch() :
EquivalenceRegion
,
Geometry
setPrecisionTrigger() :
Tally
setRadius() :
ZCylinder
setSourceSamplingRadius() :
Geometry
setSpatialType() :
Geometry
setTallies() :
DerivedTally
setTallyDomainType() :
Tally
setTallyName() :
DerivedTally
setTallyType() :
Tally
setTemperature() :
Isotope
setThermalScatteringCutoff() :
Isotope
setVolume() :
Region
setX() :
XPlane
setX0() :
ZCylinder
setY() :
YPlane
setY0() :
ZCylinder
start() :
Timer
stop() :
Timer
subtractDoubles() :
Tally
subtractFloats() :
Tally
subtractIntegers() :
Tally
Surface() :
Surface
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