Treatment of low level radioactive liquid waste containing appreciable concentration of TBP degraded products

Journal of Hazardous Materials

Volumn 196, Issue , 2011, Pages 22-28

  Valsala, T P ^a   Sonavane, M S ^a   Kore, S G ^a   Sonar, N L ^a   De, Vaishali ^a   Raghavendra, Y ^a   Chattopadyaya, S ^a   Dani, U ^a   Kulkarni, Y ^a   Changrani, R D ^a  

^a BHABHA ATOMIC RESEARCH CENTRE   (India)

Author keywords

Barium sulphate; Co precipitation; Ion exchange; Low level radioactive liquid waste; Nickel sulphide; Vitrification

Indexed keywords

BARIUM SULPHATES; CHEMICAL CO-PRECIPITATION; CHEMICAL DURABILITY; CHEMICAL TREATMENTS; CO-PRECIPITATION PROCESS; DEGRADED PRODUCTS; EFFLUENT STREAMS; HIGH CONCENTRATION; HIGH-LEVEL RADIOACTIVE LIQUID WASTE; INTERMEDIATE LEVEL; ION-EXCHANGE TREATMENT; LOW LEVEL; NICKEL SULPHIDE; RADIOACTIVE LIQUID WASTE; TRIBUTYL PHOSPHATE; WASTE PRODUCTS; WASTE STREAM;

ALKALINITY; BARIUM; CARBONATES; COMPRESSIVE STRENGTH; ION EXCHANGE; IONS; ISOTOPES; LIQUIDS; PRECIPITATION (CHEMICAL); RADIOACTIVE WASTE VITRIFICATION; RADIOACTIVITY; WASTE TREATMENT;

EFFLUENTS;

CARBONIC ACID; RUTHENIUM 106; TECHNETIUM 99M; TRIBUTYL PHOSPHATE; YTTRIUM 90;

ACIDITY; ALKALINITY; COMPRESSIVE STRENGTH; DILUTION; ION EXCHANGE; PRECIPITATION (CHEMISTRY); RADIOACTIVE WASTE; RADIONUCLIDE; VITRIFICATION; WASTE TREATMENT;

ACIDITY; ALKALINITY; ARTICLE; COMPRESSIVE STRENGTH; EFFLUENT; HIGH LEVEL RADIOACTIVE LIQUID WASTE; ION EXCHANGE; LOW LEVEL RADIOACTIVE LIQUID WASTE; NONHUMAN; PRECIPITATION; RADIOACTIVE WASTE; VITRIFICATION; WASTE MANAGEMENT;

CHEMICAL PRECIPITATION; HYDROGEN-ION CONCENTRATION; PHOSPHORIC ACID ESTERS; RADIATION PROTECTION; RADIOACTIVE WASTE; WASTE DISPOSAL, FLUID;

EID: 80455174597     PISSN: 03043894     EISSN: 18733336     Source Type: Journal    
DOI: 10.1016/j.jhazmat.2011.08.065     Document Type: Article

References (16)

1. IAEA Technical Reports Series no. 101, IAEA, Vienna, Austria, 1970.
2. IAEA Safety Series 111- F, 1995.
3. R.G. Yeotikar, M.S. Sonavane, J.G. Shah, R. Kanwar, Development of vitrified matrix for high level waste and its characterization - experience at WIP, Tarapur, SMART-93, 1993.
4. Kanwar R., Samuel M.T. Modified pot glass process for vitrification of high level radioactive waste - process engineering aspects. XIV International Congress on Glass, vol. II 1986, 399-409.
5. Raj K., Prasad K.K., Bansal N.K. Nucl. Eng. Des. 2006, 236.
6. Y. Kulkarni, S.K. Samanta, S.Y. Bakre, K. Raj, M.S. Kumra, Process for treatment of intermediate level radioactive waste based on radionuclides separation, WM-96, 1996.
7. Yeotikar R.G., Kaushik C.P., Gabriel J., Kanwar R. Treatment of alkaline intermediate level radioactive waste. NUCAR 1995, 95.
8. IAEA, Tech. Report. Series No. 222 (1983) b.
9. Berak L., Uher E., Marhol M. At. Energy Rev. 1975, 13.
10. Ozarde P.D., Samanta S.K., Raj K. Proceedings of the IAEA international conference on issues and trends in radioactive waste management - IAEA-CN-90/51 2002.
11. G.H. Jeffery, J. Bassett, J. Mendham, R.C. Denney, Vogel's Text Book of Quantitative Chemical Analysis, sixth ed., p. 452.
12. Singh U.S., Mishra A., Yeotikar R.G., Kanwar R. Immobilisation of intermediate level alkaline radioactive liquid waste in cement matrix. NUCAR 1995, 95.
13. United State Department of Energy, Nuclear Waste Management Material Hand book (test methods), Rep. DOE/TIC-11400 (1981).
14. F.A. Cotton, G. Wilkinson, Advanced inorganic chemistry. A Comprehensive Text, Third ed.
15. N.K. Bansal, S. Kumar, C.P. Kaushik, R.R. Rakesh, S.M. Galande, Safety assessment of radioactive waste packages for disposal in near surface disposal facilities, long term behaviour of low and intermediate level waste packages under repository conditions, IAEA-TECDOC-1397. pp. 101-118 (2004).
16. C. Verghese, A.K. Govindan, P.K. Wattal, T.K. Theyyunni, Cementitious matrices for intermediate level aqueous radioactive wastes BARC report BARC/1995/E/004 (1995).