Zobrazeno 1 - 5
of 5
pro vyhledávání: '"V. S. Ermolin"'
Autor:
L. V. Arseenkov, A. M. Safiulina, V. I. Volk, K. N. Dvoeglazov, D. V. Zverev, M. V. Logunov, V. S. Ermolin
Publikováno v:
Radiochemistry. 64:338-343
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::8ad9c58c6941f9f39ab661926f8ad72b
https://doi.org/10.1134/s1066362222030109
https://doi.org/10.1134/s1066362222030109
Autor:
V. I. Volk, L. V. Arseenkov, A. M. Safiulina, K. N. Dvoeglazov, D. V. Zverev, M. V. Logunov, V. S. Ermolin
Publikováno v:
Radiochemistry. 64:344-348
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::c98d47cede5698d0af48cdcd5487147f
https://doi.org/10.1134/s1066362222030110
https://doi.org/10.1134/s1066362222030110
Autor:
A. A. Murzin, Yu. S. Fedorov, N. D. Goletskii, G. Sh. Batorshin, K. V. Bugrov, N. G. Yakovlev, A. A. Naumov, V. S. Ermolin, B. Ya. Zilberman, I. V. Blazheva, N. V. Logunov, A. S. Kudinov, Yu. A. Voroshilov, S. V. Baranov, M. S. Agafonova-Moroz
Publikováno v:
Radiochemistry. 57:292-306
A process was developed for extraction recovery of 99Mo from irradiated enriched uranium target. Dissolution of the uranium–aluminum composite in nitric acid in the presence of fluoride ions with the addition of mercury ions, which are subsequently
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::9cf7746aed116d81fe418f3e52a4a2b0
https://doi.org/10.1134/s1066362215030108
https://doi.org/10.1134/s1066362215030108
Autor:
A. N. Mashkin, A. Yu. Shadrin, A. A. Murzin, Yu. S. Fedorov, V. S. Ermolin, S. A. Rodionov, B. Ya. Zilberman, N. D. Goletsky, A. S. Kudinov, and D. N. Kolupaev, D. V. Ryabkov, M. V. Logunov, L. V. Sytnik
Publikováno v:
Atomic Energy. 114:344-354
Model and real solutions are used to study and monitor the dissolution and extraction operations in the reprocessing of spent fuel AM(B) based on uranium oxide or uranium-molybdenum alloy (alloy OM-9, 9% molybdenum) with a sublayer of mass 12% compri
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::fae1fdc73a51b138c9d7a08cc52ef314
https://doi.org/10.1007/s10512-013-9722-y
https://doi.org/10.1007/s10512-013-9722-y
Autor:
E. G. Kudryavtsev, S.N. Kirillov, A. S. Kudinov, A.V. Haperskaya, V. S. Ermolin, S. A. Rodionov, M. V. Logunov, N. D. Goletskiy, T.V. Smelova, A. Yu. Shadrin, B. Ya. Zilberman, D. N. Kolupaev, Yu. S. Fedorov
Publikováno v:
Procedia Chemistry. 7:98-103
For the purpose of reprocessing of irradiated nuclear fuel from the water-cooled graphite-moderated pressure-tube reactor named AMB from decomissioned Russian “Atom Peaceful Big”, modernization of the process flow-sheet of the RT-1 plant is being
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::01de40cf84cf54694622000e38622b93
https://doi.org/10.1016/j.proche.2012.10.018
https://doi.org/10.1016/j.proche.2012.10.018