Iron and radioactivity transport code package for multiple CANDU designs

To ensure the safe and reliable operation of nuclear reactors, predictive modelling of iron and activity transport is a necessary tool for examining how changes to key chemistry parameters impact the distribution of corrosion products and corresponding radiation field growth trends. The safe and reliable operation of the Canada Deuterium Uranium (CANDU) fleet can be greatly supported by a code that is flexible, validated for multiple station designs, and models material and radioactivity transport. This work shows the development of a new code, Transport of Radioactivity and Chemistry in CANDU Reactors (TRaCCR) that combines features from the Activity Transport CANDU (ACTTRANCAN) and Corrosion and Radioactivity Transport Analysis (CARTA) codes. The functionality of TRaCCR is described, highlighting its ability to model additional CANDU station designs. The new code is adaptive to changes to station parameters such as materials of construction and chemistry specifications. TRaCCR output for a CANDU-6 design was compared to previously validated ACTTRANCAN output for validation of the new code. Ongoing work includes validation of the alternate CANDU layout using station data from relevant stations and the addition of more station layouts.