摘要
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 1300 ℃ for the incorporation of SrO in rutile Ti O2. Perovskite type Sr TiO3 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 Sr TiO3 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 0.1g·m^-2·d^-1, which is about 3 orders of magnitude higher than the LR（Ti） value.
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 1300 ℃ for the incorporation of SrO in rutile Ti O2. Perovskite type Sr TiO3 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 Sr TiO3 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 0.1g·m^-2·d^-1, which is about 3 orders of magnitude higher than the LR（Ti） value.
基金
Funded by the National Natural Science Foundation of China(No.51202203)
the Young Outstanding Scientist Fund(No.13zx9108)
the Open Project of Southwest University of Science and Technology(No.14tdfk02)
