Depletion calculation, held in memory during operation.
Return dictionary mapping cell to flux or power for current depletion step.
Return dictionary mapping cell to one-group microscopic cross-sections for current depletion step.
Return cell ORIGEN calculuation for current depletion step.
Return dictionary mapping cell to isotope to moles for current depletion step.
Return cell decay power for current depletion step.
Return cell thermal power for current depletion step.
Return cell coolant density calculuations for current depletion step.
Return MCNP input filename for current depletion step.
Return if transport is to be performed even when it is not needed for transmutation.
Return cell fuel temperature calculuations for current depletion step.
Return excited fraction states for isotope of a ORIGEN2 sublibrary.
Return previously performed coolant density calculations.
Return previously performed fuel temperature calculations.
Return characteristic multiplication factor standard deviation.
Execute transmute concurrently for a cell.
Execute transmute concurrently for each cell.
Pickle for depletion calculation.
Pickle for depletion step.
Return dictionary mapping cell to decay power for this depletion step.
Return dictionary mapping cell to decay power for next depletion step.
Return one-group microscopic cross-sections of a cell for this depletion step.
Return cell ORIGEN calculuation for this depletion step.
Return dictionary mapping isotope to mass density of a cell for this depletion step.
Return dictionary mapping isotope to number density of a cell for this depletion step.
Return dictionary mapping isotope to moles of a cell for this depletion step.
Return cell coolant density calculuations for this depletion step.
Return cell fuel temperature calculuations for this depletion step.
Execute gnuplot and convert the resulting eps to png and pdf.
Return if a reaction is of interested for an isotope.
Derive compositions from arbitary isotopic mixtures.
MCNP cell fission energy deposition tally.
MCNP input file parser.
Return path for a cell which appears in multiple root cells.
MCNP output file parser.
Derive one-group microscopic cross-section for a cell, isotope, and reaction.
Return power for a cell using a number of reaction Q-values.
Derive reaction rate for a cell, isotope, and reaction.
Parser for mocdown input file.
Statistical random variable.
Return expected value.
Return relative standard deviation.
Return relative variance.
Return expected value.
Return relative standard deviation.
Recycle calculation, held in memory during operation.
Return if isotopics of subsequent cycles have converged.
Determine the slope of a set of points using a simple linear regression.
MCNP tally parser.
Return energy bin values.
Find a unique integer, given a number of digits and container of forbidden integers.