Tritium Transport Analysis in Sodium-Cooled Fast Reactors

A tritium permeation analysis code (SFR-TPC) was developed to analyze tritium distributions in Sodium- Cooled Fast Reactors (SFRs) systems. The MATLAB software was used for developing this code. The SFRTPC is based on mass balance equations regarding various chemical forms of hydrogen (i.e. T-, HT, HTO), coupled with a variety of tritium sources, sinks, and permeation models. In the SFR-TPC, ternary fission and neutron capture reactions of B10 were taken into considerations as tritium sources. Permeation of tritium through pipes, vessels, and heat exchangers were considered as the main tritium transport paths. In addition an isotope exchange model was developed to analyze tritium isotopes distribution in water. In literature, different tritium transport codes were developed for other types of nuclear plants, such as the TPAC code, developed for HTGR plants. The objective of this work is to evaluate tritium inventories and tritium losses inside and from a SFR plant respectively.