Treatment feasibility of highly alkaline and highly radioactive liquid waste—a novel approach

Author:

Sonar N. L.,Sen S.,Thakur D. A.,Mittal V. K.,P.Valsala T.,Sathe D. B.,Bhatt R. B.

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

Reference34 articles.

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2. Kanwar R, Samuel MT (1986) Modified pot glass process for vitrification of high level radioactive waste—process engineering aspects. In: XIV international congress on glass, vol II, pp 399–409

3. Raj K, Prasad KK, Bansal NK (2006) Radioactive waste management practices in India. Nucl Eng Des 236:914–930

4. Mishra S, Soda AK, Sridhar M, Mallika C, Pandey NK, Kamachi Mudali U (2018) Identification of diluent degradation products in radiolyzed PUREX solvent. Solvent Extr Ion Exch 36(1):54–65

5. Kulkarni Y, Samanta SK, Bakre SY, Raj K, Kumra MS (1996) Process for treatment of intermediate level radioactive waste based on radionuclides separation. Proc. Int. Symp Tucson, AZ, 1996, Arizona Board of Regents, Phoenix, AZ Proceeding of WM-96

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