Performance of Cement for Immobilizing Strontium Waste in Saline Environment

DOI: 10.4236/msa.2013.412A002   PDF   HTML     2,454 Downloads   3,883 Views  


For solving the radioactive waste storage problem, there is an idea to store immobilized waste at deep sea. Solidifier material, such as cement should be resistance to saline environment for deep sea storage. So, this research objective is to study the performance of cementation method in immobilizing strontium waste in saline environment. Research was conducted by immobilizing strontium waste using Portland pozzolanic cement, white cement and composite Portland cement. Cement, 65 ppm Sr(NO3)2, sand and water were mixed and cast. Strontium waste varied in 2 v/o, 4 v/o, 6 v/o and 8 v/o. After 28 days curing, the cement block’s compressive strength and leaching rate on saline water were analyzed. Determination of compressive strength was done by using Universal Wood Testing. The density of blocks was measured by picnometer at 25°C. Compressive strength test for Portland pozzolanic cement at various w/c was conducted to confirm the effect of w/c in increasing the strength. For testing strontium leaching rate in water containing 35 ppm NaCl, cement blocks have been immersed in saline water for 21 days. 25 ml samples were taken and analyzed by Atomic Absorption Spectrophotometer. Strontium leaching rate on block containing pH 9 of waste was compared to the previous research data of strontium leaching rate on water to know the effect of saline water. To adjust the pH, 1 MNaOH was added into the waste. Effects of various cement type and filler materials (sand, zeolite and baryte) on Portland pozzolanic cement were also compared. The results show that there were almost no effects of salt on immobilized strontium waste, except in pH 9 waste (0.00224 over to0.000199 g/cm2·days). Strontium leaching rates on all cemented waste still meet the IAEA’s standard, so the safety of cemented strontium waste disposal at saline environment could be ensured.

Share and Cite:

S. Putero and W. Rosita, "Performance of Cement for Immobilizing Strontium Waste in Saline Environment," Materials Sciences and Applications, Vol. 4 No. 12A, 2013, pp. 7-11. doi: 10.4236/msa.2013.412A002.

Conflicts of Interest

The authors declare no conflicts of interest.


[1] Y. S. Tang and J. H. Saling, “Radioactive Waste Management,” Hemisphere Publishing Corporation, New York, 1990.
[2] M. I. Ojovan and W. E. Lee, “An Introduction to Nuclear Waste Immobilisation,” Elsevier Inc., Oxford, 2005.
[3] S. H. Putero, W. Rosita, et al., “The Performance of Various Pozzolanic Materials in Improving Quality of Strontium Liquid Waste Cementation,” Procedia Environmental Science, Vol. 17, 2013, pp. 703-710.
[4] A. A. Prabaningrum and W. A. W. Supardi, “The Effect of Ca-Bentonite Additive on the Cementation of Radioactive Concentrate Waste Containing Sodium Nitrate,” Proceedings of the 2nd Biannual International Workshop on High Level Radioactive Waste Management, Yogyakarta, 10-12 August 1999, pp. 81-90.
[5] H. Poernomo and R. dan Supardi, “Pengaruh Natrium Silikat Terhadap Sementasi Limbah Uranium yang Mengandung Ammonium Flourida,” Prosiding Pertemuan dan Presentasi Ilmiah Penelitian Dasar Ilmu Pengetahuan dan Teknologi Nuklir, Yogyakarta, 25-27 April 1995, pp. 340-345.
[6] D. C. MacLaren and M. A. dan White, “Cement: Its Chemistry and Properties,” Journal of Chemical Education, Vol. 80, No. 6, 2003, pp. 623-635.

comments powered by Disqus

Copyright © 2020 by authors and Scientific Research Publishing Inc.

Creative Commons License

This work and the related PDF file are licensed under a Creative Commons Attribution 4.0 International License.