TiO2 was employed as the waste form for disposal of simulated nuclide Sr. Preparation of Sr bearing rutile was explored under different sintering temperatures and Sr contents. The optimal treatment temperature was confirmed as 1 300 ℃ for the incorporation of SrO in rutile TiO2. Perovskite type SrTiO3 was prepared as the resultant product. The limited containment capacity of SrO in rutile was speculated to be 56.5wt%. As the SrO content increases, the as-synthesized sample exhibits more porosity because SrTiO3 phase demonstrates higher density than rutile and SrO. The 28 day normalized leaching rate (LRi) of Sr and Ti will decrease congruously as the SrO incorporation increases. The LRSr value is lower than 0.1 g·m-2·d-1, which is about 3 orders of magnitude higher than the LRTi value.