.TRANSFORM.Nuclear.ReactorKinetics.SparseMatrix.Functions.Initial_FissionProducts

Interface

function Initial_FissionProducts
  extends TRANSFORM.Icons.UnderConstruction;
  extends TRANSFORM.Icons.Function;
  input Integer nC "# of isotopes";
  input SIadd.NeutronFlux phi "Neutron flux";
  input SIadd.InverseTime[nC] lambdas "Half-life of fission product";
  input Integer l_lambdas_col[:];
  input Integer l_lambdas_count[nC];
  input Real l_lambdas[size(l_lambdas_col, 1)] = fill(0, size(l_lambdas_col, 1)) "need to correct uni - Matrix of parent sources (e.g., sum(column) = 0, 1, or 2)*lambdas for each fission product 'daughter'. Row is daughter, Column is parent.";
  input SI.Area sigmasA[nC] = fill(0, nC) "Microscopic absorption cross-section for reactivity feedback";
  input Integer f_sigmasA_col[:];
  input Integer f_sigmasA_count[nC];
  input Real f_sigmasA[size(f_sigmasA_col, 1)] = fill(0, size(f_sigmasA_col, 1)) "need to correct units";
  input SIadd.ExtraPropertyExtrinsic mCs_guess[nC] "Number of fission product atoms per group per volume";
  input Integer i_noGen[:] = {0};
  output SIadd.ExtraPropertyExtrinsic mCs[nC];
end Initial_FissionProducts;