There has been a growing interest in modelling the material degradation and transport mechanisms that lead to elevated radiation fields in the primary heat transport system (PHTS) of nuclear reactors. Meanwhile, online monitoring for flow accelerated corrosion (FAC) could have significant impacts on station FAC management programs providing real-time corrosion rate information. The Corrosion and Radioactivity Transport Analysis (CARTA) code has been under development at UNB since 1996 and is a one-dimensional, comprehensive simulation package that mechanistically unifies the various material and activity transport processes in a typical, 600 MWe Canada Deuterium Uranium (CANDU-6) nuclear reactor. The output of the object-oriented code includes flow-accelerated corrosion (FAC) rate and active and inactive elemental composition in the coolant and circulating crud. CARTA is adaptive to changes in materials of construction and incorporates kinetics, mass transfer, material wear, and a detailed boiler thermal-hydraulic model, which has been benchmarked to station data. The concept of hydrogen flux monitoring for assessment of FAC in CANDU reactors was validated at the Canadian Nuclear Laboratories and the commercial application was developed at the CNER, with the first successful deployment at the Point Lepreau Nuclear Generating Station (PLNGS) in 2006. Operation of Hydrogen Effusion Probe (HEPro™) both pre- and post-refurbishment at PLNGS has demonstrated the viability of measuring the FAC rate on outlet feeders, in-situ and in real-time, which has been incorporated into the CARTA code. This paper presents material and activity transport simulations for a typical CANDU-6 reactor, including post-station refurbishment and the capability of the HEPro is highlighted.