In this paper, detailed verification and experimental validation of the formulations and algorithms of the Multi-stage Response-function Transport (MRT)–based Real-time Analysis for Particle-transport and In-situ Detection (RAPID) code system is presented. In particular, RAPID’s fission matrix formulation for eigenvalue calculations and its detector response function for reaction rate calculations have been examined in this study. As part of a collaboration between Virginia Tech and the Jožef Stefan Institute (JSI), RAPID is used to simulate dosimetry experiments performed at the JSI TRIGA Mark II reactor. In these measurements, wire dosimeters are irradiated at different axial and radial locations in the reactor, and their signature activity is measured. The RAPID calculations require the determination of the fission neutron source distribution and the Au(n,)Au reaction rates in the wires. In addition, the Monte Carlo code Serpent is used for comparison of the RAPID-calculated criticality eigenvalue, three-dimensional fission neutron source distribution. The validation results show excellent agreement of RAPID with both the experiments and the reference Serpent calculation, with an average relative difference of about 3% with respect to the measurements.