Back end of Indian nuclear fuel cycle-A road to sustainability
- 1 November 2017
- journal article
- Published by Elsevier BV in Progress in Nuclear Energy
- Vol. 101, 133-145
- https://doi.org/10.1016/j.pnucene.2017.03.004
Abstract
No abstract availableThis publication has 7 references indexed in Scilit:
- Process development for separation of cesium from acidic nuclear waste solution using 1,3-dioctyloxycalix[4]arene-crown-6 + isodecyl alcohol/ n -dodecane solventSeparation and Purification Technology, 2014
- Studies on hydrolysis and radiolysis of tetra(2-ethylhexyl)diglycolamide (TEHDGA)/isodecyl alcohol/n-dodecane solvent systemRadiochimica Acta, 2010
- Process Development for Bulk Separation of Trivalent Actinides and Lanthanides from Radioactive High-Level Liquid WasteNuclear Science and Engineering, 2007
- Barium borosilicate glass – a potential matrix for immobilization of sulfate bearing high-level radioactive liquid wasteJournal of Nuclear Materials, 2006
- Spent fuel reprocessing: A vital link in Indian nuclear power programNuclear Engineering and Design, 2006
- Radioactive waste management practices in IndiaNuclear Engineering and Design, 2006
- Vitrification of sulphate bearing high level wastes in borosilicate matrixWaste Management, 1998