Zobrazeno 1 - 10 of 33 pro vyhledávání: '"R. V. Subba Rao"'
3
Mass transfer studies in a micromixer-settler: extraction of Cs and Sr with CCD-PEG-400 solvent from simulated acidic radwaste solutions
Autor: Shekhar Kumar, R. V. Subba Rao
Publikováno v: Journal of Radioanalytical and Nuclear Chemistry. 329:351-357
Solvent extraction of Cs(I) and Sr(II) from a simulated radwaste acidic solution was studied with chlorinated cobalt dicarbollide/polyethylene glycol-400/FS-13 solvent in a microfluidic channel based miniature extractor with qualitative extraction. E
Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::31a0781202bfd9998684a49e0226bbee
https://doi.org/10.1007/s10967-021-07754-4
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4
Thermodynamic modeling of Pu(IV) and nitric acid extraction by 1.1 M tri-iso-amyl phosphate in n-dodecane
Autor: N.K. Pandey, R. V. Subba Rao, S. Balasubramonian
Publikováno v: Journal of Radioanalytical and Nuclear Chemistry. 326:105-113
A thermodynamic model for the liquid–liquid extraction of tetravalent plutonium (Pu(IV)) by 1.1 M Tri iso Amyl Phosphate (TiAP) in n-dodecane was developed. The activity coefficients of species in the aqueous phase were estimated using eUNIQUAC act
Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::c7cd9d45681041370d2606cdfe69c086
https://doi.org/10.1007/s10967-020-07338-8
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5
Cloud point extractive spectrophotometric method for determination of uranium in raffinate streams during spent nuclear fuel reprocessing
Autor: M. Suba, D. Sivakumar, R. V. Subba Rao, K. Dhamodharan, C. K. Mukhopadhyay
Publikováno v: Journal of Radioanalytical and Nuclear Chemistry. 322:743-750
A cloud point extractive spectrophotometric method was developed for the determination of uranium in raffinate streams. Uranium was extracted to a tri n-octyl phosphine oxide in o-Xylene from raffinate. Uranium present in organic phase was analyzed b
Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::66fadb8e1a5ba7ab4084a2aaa0b9dcf3
https://doi.org/10.1007/s10967-019-06704-5
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6
Comparison of activity coefficient models for the estimation of uranyl nitrate and nitric acid distribution coefficients in phosphoric solvent
Autor: N.K. Pandey, R. V. Subba Rao, S. Balasubramonian
Publikováno v: Progress in Nuclear Energy. 128:103472
The modelling of solvent extraction system is important for the process flow sheet design and optimization. The estimation of aqueous phase activity coefficients constitutes the major part of the thermodynamic modelling of solvent extraction system.
Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::4f1270b2b834a950e2b82933202034bd
https://doi.org/10.1016/j.pnucene.2020.103472
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7
Experiences of reprocessing of plutonium-rich mixed carbide fuels
Autor: R. Natarajan, N.K. Pandey, R. V. Subba Rao, V. Vijayakumar
Publikováno v: Journal of Radioanalytical and Nuclear Chemistry. 304:401-407
Mixed carbide (70 % Pu, 30 % U) spent fuels up to a burn up of 155 GWd/Te and a cooling time of around 2 years discharged from the Fast Breeder Test Reactor (FBTR) were successfully reprocessed at COmpact Reprocessing of Advanced fuels in Lead shield
Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::b333eaf54d1f515c6dad9f4a122f1457
https://doi.org/10.1007/s10967-015-4000-1
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8
Optimization of an analytical method for reducing the volume of radioactive waste generated during determination of uranium in presence of plutonium
Autor: R. V. Subba Rao, M. Suba, A. Nageswara Rao, P. Velavendan, N.K. Pandey, U. Kamachi Mudali
Publikováno v: Journal of Radioanalytical and Nuclear Chemistry. 303:631-636
A new method for uranium (U) determination in presence of plutonium (Pu) in the range of 0.7–2.4 mg per aliquot is optimized in a low volume potentiometric cell (4 mL) and waste volume is decreased by six times. U determination in presence Pu at hi
Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::e5fbcd0f195db10f10e8e4921a3072d2
https://doi.org/10.1007/s10967-014-3611-2
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9
Optimization of Flowsheet for Scrubbing of Ruthenium during the Reprocessing of Fast Reactor Spent Fuels
Autor: S. Pugazhendi, R. Natarajan, K. Dhamodharan, R. V. Subba Rao, V. Vijayakumar, N.K. Pandey, Pradeep Kumar Sharma
Publikováno v: Separation Science and Technology. 48:2494-2498
The solvent extraction method using tri-n-butyl phosphate diluted with heavy normal paraffin is being used as an extractant for the recovery of plutonium and uranium present in spent fuel discharged from a nuclear reactor. The purification of uranium
Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::5c38c6e61365f4a86f273d4ef08878d1
https://doi.org/10.1080/01496395.2013.807828
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10
Studies on understanding the mechanism of the enhanced conductivity of the third phase in PUREX process during reprocessing of fast reactor fuel
Autor: A. Nageswara Rao, S. Subbuthai, Prasana Sahoo, R. V. Subba Rao
Publikováno v: Journal of Radioanalytical and Nuclear Chemistry. 295:943-949
Towards development of electrical conductivity based sensors for online detection of formation of third phase during reprocessing of Pu rich spent nuclear fuels, laboratory studies were carried out using U4+ solutions in various experimental conditio
Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::c76a3663eb1844b1080fc60e854b2d1d
https://doi.org/10.1007/s10967-012-2279-8
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