function Initial_FissionProducts input Integer nC "# of fission products"; input Integer nFS "# of fission product sources"; input Integer nT "# of fission product types (e.g., fast/thermal)"; input Real[nC, nC] parents "Matrix of parent-daughter sources"; input Units.NonDim fissionSources_start[nFS] = fill(1/nFS, nFS) "Fission source material fractional composition (sum=1)" annotation( Dialog(tab = "Initialization", group = "Fission Sources")); input Units.NonDim fissionTypes_start[nFS, nT] = fill(1/nT, nFS, nT) "Fraction of fission from each fission type per fission source, sum(row) = 1" annotation( Dialog(tab = "Initialization", group = "Fission Sources")); input SI.Energy w_f_start = 200e6*1.6022e-19 "Energy released per fission" annotation( Dialog(tab = "Initialization", group = "Fission Sources")); input SI.MacroscopicCrossSection SigmaF_start = 1 "Macroscopic fission cross-section of fissile material" annotation( Dialog(tab = "Initialization", group = "Fission Sources")); input SI.Area sigmasA_start[nC] "Microscopic absorption cross-section for reactivity feedback" annotation( Dialog(tab = "Initialization", group = "Fission Products")); input Real fissionYields_start[nC, nFS, nT] "# fission product atoms yielded per fission per fissile source [#/fission]" annotation( Dialog(tab = "Initialization", group = "Fission Products")); input Units.InverseTime lambdas_start[nC] "Decay constants for each fission product" annotation( Dialog(tab = "Initialization", group = "Fission Products")); input SIadd.ExtraPropertyExtrinsic mCs_guess[nC] "Number of fission product atoms per group per volume" annotation( Dialog(tab = "Initialization")); input SI.Power Qs_fission_start = 1e6 "Power determined from kinetics. Does not include fission product decay heat" annotation( Dialog(tab = "Initialization")); input SI.Volume Vs_start = 0.1 "Volume for fisson product concentration basis" annotation( Dialog(tab = "Initialization")); output SIadd.ExtraPropertyExtrinsic mCs[nC]; end Initial_FissionProducts;