The radionuclide concentration into the disposal system compartments of Saligny near surface repository is used as safety indicator in order to demonstrate the safety. The disposal system of Saligny near surface repository consists of waste form itself, engineered barriers and natural barriers. The conceptual model of Saligny near surface repository as well as the natural barriers characteristics are described. For the aim of calculation, the disposal system is splitted into eight compartments: waste form, slab foundation, foundation ground, silty loess, clayey loess, red clay, pre-quaternary clay, Barremian limestone. The concentration of the 3H, 60Co, 137Cs, 14C, 90Sr, 99Tc and 129I isotopes in each disposal compartment of Saligny repository is calculated by using AMBER computer code and graphically represented. In order to demonstrate the safety of the disposal system, the calculated values of safety indicators are compared with the regulatory limits for drinking water.
