The purpose of this study is to assess tritium control aspects of fusion reactors, to derive a preliminary estimate of the probable tritium releases and source terms under steady-state reactor operation, and to identify areas where advancement of fusion reactor tritium control technology will be required. Tritium release aspects of six fusion reactor conceptual designs were evaluated, including four Tokamaks, one mirror and one theta pinch reactor. The principal effort was directed to Tokamaks because they represent the current main-line Division of Magnetic Fusion Energy (DMFE) effort. Two tokamaks which had the most detailed conceptual designs at the time of the analysis (PPPL and UWMAK-I) were selected for detailed analysis to define tritium source terms.