Please use this identifier to cite or link to this item: http://hdl.handle.net/10603/375499
Title: Thermodynamic Model for the Prediction of Distribution coefficient of Major Solutes in Tri alkyl Phosphates for Flow sheet Development in Spent Nuclear Fuel Reprocessing
Researcher: S. BALASUBRAMONIAN
Guide(s): R V Subba Rao
Keywords: Activity coefficient
Distribution coefficient
Electrolyte Universal Quasi Ch
Nitric acid
Nuclear fuel reprocessing
Plutonium
Solvent Extraction
Tri iso amyl phosphate (TiAP)
Tri n-Butyl Phosphate (TBP)
Uranium
University: Homi Bhabha National Institute
Completed Date: 2022
Abstract: newline
Pagination: 
URI: http://hdl.handle.net/10603/375499
Appears in Departments:Department of Engineering Sciences

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02_certificate.pdf858.4 kBAdobe PDFView/Open
03_prelim.pdf1.78 MBAdobe PDFView/Open
04_content.pdf388.25 kBAdobe PDFView/Open
05_synopsis.pdf354.76 kBAdobe PDFView/Open
06_tabfiglist.pdf390.71 kBAdobe PDFView/Open
07_chap1.pdf605.02 kBAdobe PDFView/Open
08_chap2.pdf782.95 kBAdobe PDFView/Open
09_chap3.pdf768.03 kBAdobe PDFView/Open
10_chap4.pdf1.35 MBAdobe PDFView/Open
11_chap5.pdf1.06 MBAdobe PDFView/Open
12_chap6.pdf1.41 MBAdobe PDFView/Open
19_summary.pdf378.38 kBAdobe PDFView/Open
20_other_info.pdf345.66 kBAdobe PDFView/Open
21_highlights.pdf560.86 kBAdobe PDFView/Open
80_recommendation.pdf534.8 kBAdobe PDFView/Open
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