Zobrazeno 1 - 5
of 5
pro vyhledávání: '"R. K. Malav"'
Publikováno v:
Analytical methods : advancing methods and applications. 3(3)
ThO2 with approximately 3% 233UO2 is the proposed fuel for the Advanced Heavy Water Reactor (AHWR) and characterized as a mixed oxide (MOX) fuel. Due to the existence of a single oxidation state, quantitative dissolution of MOX samples like (Th-U)O2
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=pmid________::45cf7e4d83bc57a74df95dd21c8c8daa
https://pubmed.ncbi.nlm.nih.gov/32938082
https://pubmed.ncbi.nlm.nih.gov/32938082
Autor:
Dasarathi Das, Gurwinder Singh, Neeta Save, P.G. Behere, Amba Mishra, R. K. Malav, Arun Kumar, Bholanath Mahanty, Mohd Afzal, Pradeep Kumar
Publikováno v:
Journal of Radioanalytical and Nuclear Chemistry. 309:1159-1168
A significant quantity of plutonium bearing scrap was getting generated during the fabrication of (U,Pu)O2 mixed oxide fuel for Indian Prototype Fast Breeder Reactor. This document assesses the feasibility of carrying out recycling of the impure scra
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::de8e50cf13947a7a68481047bd9170fd
https://doi.org/10.1007/s10967-016-4715-7
https://doi.org/10.1007/s10967-016-4715-7
Publikováno v:
Journal of Radioanalytical and Nuclear Chemistry. 308:495-503
(Th,Pu)O2 fuel pellets were synthesised by coated agglomerate pelletization route and characterized for the chemical quality control. (Th,Pu)O2 pellets were characterized for trace metals by spectrometric methods and non metals by ion chromatographic
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::e151b04856ef47d0fb4df2cbbc524a70
https://doi.org/10.1007/s10967-015-4411-z
https://doi.org/10.1007/s10967-015-4411-z
Publikováno v:
Journal of Radioanalytical and Nuclear Chemistry. 295:425-430
Microwave heating technique has the unique advantages of low processing time, less consumption of reagents, homogeneous heating and maintenance-free adaptability to glove box. Dissolution of thorium and plutonium containing fuel viz sintered thorium
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::550edbfaf9ad14b0dd6e88033a1c6515
https://doi.org/10.1007/s10967-012-1790-2
https://doi.org/10.1007/s10967-012-1790-2
Autor:
G Singh, J. P. Panakkal, Rakesh Kumar Singhal, R. K. Malav, Ajit Fulzele, Afzal, Amrit Prakash
Publikováno v:
Analytical Methods. 3:622
ThO2 with approximately 3% 233UO2 is the proposed fuel for the Advanced Heavy Water Reactor (AHWR) and characterized as a mixed oxide (MOX) fuel. Due to the existence of a single oxidation state, quantitative dissolution of MOX samples like (Th–U)O
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::fbe721216642d240e80003ff61aa6f96
https://doi.org/10.1039/c0ay00630k
https://doi.org/10.1039/c0ay00630k