Whether they are based on fusion (JET, ITER, DEMO) or fission (e.g., CANDU type) or are cooled using molted salts [molten salt reactors (MSRs)], nuclear reactors generate significant amounts of waste in the form of low-level tritiated light water or heavy water, which generates risks for the environment and radiological risks for operating personnel. Given the wide range of tritium concentrations of tritiated water waste, processing it efficiently is possible only if the process is based on the combined process of liquid phase catalitic exchange and electrolysis of water. During this process, tritium is concentrated as tritiated water, which reduces the amount of waste and concentrates the water at the isotopic level high enough for further processing in view of tritium recovery, employing isotopic transfer in gas form. This paper reports on the modification of an industrial hydrogen generator in view of tritium compatibility to be used for further processing of tritiated (heavy) water for tritium recovery. Additionally, analysis will be made, and results will be presented on what will be the tritium/deuterium concentration profile in the generator and what influence the water holdup will have on the isotope concentration.