Zobrazeno 1 - 10
of 64
pro vyhledávání: '"Vrinda Devi"'
Autor:
Dixit, Rajashree, Vrinda Devi, K.V., Biju, K., Kumar, Nagendra, Hinge, A.K., Vetal, Hema, Mukhopadhyay, S.
Publikováno v:
In Applied Radiation and Isotopes September 2024 211
Publikováno v:
In Journal of Nuclear Materials May 2019 518:129-139
Publikováno v:
International Journal of Polymer Analysis & Characterization; Jul2024, Vol. 29 Issue 5, p328-345, 18p
Autor:
Ramkumar, Jayshree1 (AUTHOR), Vrinda Devi, K. V.2 (AUTHOR) kvvdevi@barc.gov.in
Publikováno v:
Journal of Radioanalytical & Nuclear Chemistry. Oct2022, Vol. 331 Issue 10, p4361-4367. 7p. 2 Color Photographs, 1 Black and White Photograph, 3 Charts, 3 Graphs.
Autor:
Jayshree Ramkumar, K. V. Vrinda Devi
Publikováno v:
Journal of Radioanalytical and Nuclear Chemistry. 331:4361-4367
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::09c82112b3f80fdcd4dbaa74432415c0
https://doi.org/10.1007/s10967-022-08491-y
https://doi.org/10.1007/s10967-022-08491-y
Autor:
Vrinda Devi, K. V.1 (AUTHOR) kvvdevi@barc.gov.in, Ramkumar, Jayshree2 (AUTHOR), Biju, K.3 (AUTHOR), Sathe, D. B.4 (AUTHOR)
Publikováno v:
Journal of Radioanalytical & Nuclear Chemistry. Feb2021, Vol. 327 Issue 2, p913-922. 10p. 1 Color Photograph, 3 Black and White Photographs, 3 Diagrams, 3 Charts, 8 Graphs.
Autor:
Vrinda Devi, K.V., Panakkal, J.P.
Publikováno v:
In Nuclear Engineering and Design February 2013 255:132-137
Publikováno v:
Journal of Radioanalytical and Nuclear Chemistry. 327:913-922
Image analysis and spectroscopic method of evaluation are applied on Gamma auto radiographs (GAR) to assess the effect of plutonium concentration in (U,Pu)O2 mixed oxide (MOX) fuel samples on the characteristics of the irradiated film. Results of the
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::484e738a78893b92a63d9e0ee0ea6888
https://doi.org/10.1007/s10967-020-07561-3
https://doi.org/10.1007/s10967-020-07561-3
Publikováno v:
In Nuclear Engineering and Design May 2011
Publikováno v:
Journal of Nuclear Materials. 518:129-139
(U,Pu)O2 mixed oxide (MOX) fuel has been irradiated in thermal as well as fast reactors in India for Pu utilization. MOX fuels are conventionally fabricated through the powder metallurgical route in conformance with the quality specifications. Homoge
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::71eb593a5de113881e423eebe172d4a2
https://doi.org/10.1016/j.jnucmat.2019.02.048
https://doi.org/10.1016/j.jnucmat.2019.02.048