Recovery of molybdenum by solvent extraction from simulated high level liquid waste

Author:

Chikkamath Santosh S.,Patil Dinesh M.,Kabadagi Anand S.,Tripathi Vaidehi S.,Kar Aishwarya S.,Manjanna Jayappa

Funder

BRNS/ DAE

DST-FIST

Publisher

Springer Science and Business Media LLC

Subject

Health, Toxicology and Mutagenesis,Public Health, Environmental and Occupational Health,Spectroscopy,Pollution,Radiology, Nuclear Medicine and imaging,Nuclear Energy and Engineering,Analytical Chemistry

Reference60 articles.

1. Lutze W (1988) In: Luntze W, Ewing Amstedm RC (eds) Silicate glasses in radioactive waste forms for the future, No. 17, vol 20. North Holland, Amsterdam, pp 1–59

2. Schiewer E, Rabe H, Weisenburger S (1982) The materials balance-scientific fundamentals for the quality assurance of vitrified waste. Sci Basis Radioact Waste Manag V11:289–297

3. Kaushik CP, Mishra RK, Shengupta P, Kumar A, Das D, Kale GB, Raj K (2006) Barium borosilicate glass-a potential matrix for immobilization of sulfate bearing high-level radioactive waste. J Nucl Mater 358:129–138

4. Sengupta P, Mittra J, Kale G (2006) Interaction between borosilicate melt and inconel. J Nucl Mater 350:66–73

5. Valsala TP, Joseph A, Yeotikar RG (2001) Study of yellow phase formation during vitrification of high level radioactive liquid waste. In: Proceedings of BRNS-DAE national symposium on nuclear and radiochemistry (NUCAR), vol 587, pp 542–543

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