Zobrazeno 1 - 10
of 33
pro vyhledávání: '"N.L. Sonar"'
Publikováno v:
Journal of Radioanalytical and Nuclear Chemistry. 330:811-820
Low level radioactive liquid waste (LLW) obtained after treatment of Intermediate level radioactive waste (ILW) is highly alkaline and rich in 99Tc as the pertechnetate ion. It is considered as a long-term hazard in nuclear waste disposal. Solvent ex
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::960ad75f54136823de52a58bbaf43d0a
https://doi.org/10.1007/s10967-021-07983-7
https://doi.org/10.1007/s10967-021-07983-7
Autor:
S. Pradhan, Raj B. Bhatt, Basudev Swain, Darshan B. Sathe, N.L. Sonar, V.K. Mittal, S. Ramsubramanian, T. P. Valsala, A.K. Pabby
Publikováno v:
Separation & Purification Reviews. 51:143-173
Among the various separation technologies used to treat radioactive wastes, membrane technologies have been chosen in this article since they have many advantages over conventional processes. Membr...
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::88953a3aa23aea7c317d9359874666a8
https://doi.org/10.1080/15422119.2021.1878221
https://doi.org/10.1080/15422119.2021.1878221
Publikováno v:
Journal of Radioanalytical and Nuclear Chemistry. 328:113-119
Low level radioactive liquid waste (LLW) is generated at different stages of operation of reprocessing as well as radioactive waste management. The LLW generated here is alkaline with high salt content. It contains different radioisotopes namely106Ru
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::71ec958e3fda0888abbf4148d5580564
https://doi.org/10.1007/s10967-020-07553-3
https://doi.org/10.1007/s10967-020-07553-3
Publikováno v:
Journal of Radioanalytical and Nuclear Chemistry. 330:1623-1623
The original article was published without an acknowledgment section. The complete acknowledgment section is given in this correction.
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::5b91a6ad418b778bfacec5bb733890c8
https://doi.org/10.1007/s10967-021-08008-z
https://doi.org/10.1007/s10967-021-08008-z
Akademický článek
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Autor:
Vaishali De, N.L. Sonar, Y. Raghavendra, T.P. Valsala, M.S. Sonavane, Savita Jain, Y. Kulkarni, R.D. Changrani
Publikováno v:
DESALINATION AND WATER TREATMENT. 38:22-28
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::c244667482277eaeb04356d08991cbcd
https://doi.org/10.5004/dwt.2012.2286
https://doi.org/10.5004/dwt.2012.2286
Autor:
Y. Kulkarni, Savita Jain, R.D. Changrani, Y. Raghavendra, Vaishali De, T.P. Valsala, N.L. Sonar, M. S. Sonavane
Publikováno v:
Desalination and Water Treatment. 38:22-28
Technetium exists as pertechnate (TcO4 –) ion under oxidizing condition. It is found in almost all streams originating from reprocessing plant. The presence of 99Tc results substantial operating problems in waste management practices due to the lon
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::079083fb83ee8531eb83a9455f47b4f8
https://doi.org/10.1080/19443994.2012.664109
https://doi.org/10.1080/19443994.2012.664109
Autor:
V. Pardeshi, N.L. Sonar, Raj Kanwar, T.P. Valsala, M. S. Sonavane, Y. Raghvendra, Vaishali De, Y. Kulkarni
Publikováno v:
Journal of Radioanalytical and Nuclear Chemistry. 294:185-189
99Tc is one of the long lived fission product with high fission yield. From radioactive waste management point of view it is very much essential to evaluate the concentration of technetium in the radioactive liquid waste in order to finalise the trea
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::2a50af2e9f41b47c8cd0417d9381bb68
https://doi.org/10.1007/s10967-011-1583-z
https://doi.org/10.1007/s10967-011-1583-z
Autor:
T.P. Valsala, R.D. Changrani, S.G. Kore, U. Dani, Y. Kulkarni, N.L. Sonar, Y. Raghavendra, M. S. Sonavane, Vaishali De, S. Chattopadyaya
Publikováno v:
Journal of Hazardous Materials. 196:22-28
The acidic and alkaline low level radioactive liquid waste (LLW) generated during the concentration of high level radioactive liquid waste (HLW) prior to vitrification and ion exchange treatment of intermediate level radioactive liquid waste (ILW), r
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::ed266a05faaf0d953e1d804d1b57a022
https://doi.org/10.1016/j.jhazmat.2011.08.065
https://doi.org/10.1016/j.jhazmat.2011.08.065