Zobrazeno 1 - 6
of 6
pro vyhledávání: '"D. E. Tikhonova"'
Publikováno v:
Radiochemistry. 65:177-184
Abstract The efficiency of voloxidation of mixed nitride uranium–plutonium spent nuclear fuel (MNUP SNF) for the separation of the fuel composition from the fuel rod cladding and removal of 3H and 14C was estimated. It was shown that the completene
Publikováno v:
Radiochemistry. 64:551-580
Autor:
V. N. Momotov, E. A. Erin, A. Yu. Volkov, V. N. Kupriyanov, M. I. Khamdeev, D. E. Tikhonova, A. Yu. Shadrin, Yu. S. Khomyakov
Publikováno v:
Radiochemistry. 64:37-43
Publikováno v:
Radiochemistry. 63:364-368
A procedure for determining the specific activity of carbon-14 in samples of irradiated nuclear fuel (INF) has been developed and metrologically certified. The procedure is based on oxidation of 14C to 14CO2 and its catching with alkaline traps, foll
Publikováno v:
Radiochemistry. 63:66-71
Procedure for determining the specific activity of tritium in samples of spent nuclear fuel (SNF) was developed and methodologically certified. The procedure was used to determine the specific activity of tritium in samples of mixed nitride uranium-p
Autor:
O. S. Dmitrieva, S. S. Poglyad, A. A. Lizin, A. Yu. Shadrin, D. E. Tikhonova, Boris F. Myasoedov, V. N. Momotov, I. S. Golubenko, A. A. Kolobova, M. I. Khamdeev, M. Yu. Kalenova, Sergey E. Vinokurov, D. M. Yandaev, A. V. Dmitrieva, M. V. Dodonova, S. V. Tomilin
Publikováno v:
Radiochemistry. 62:131-137
The results of manufacturing, studying the radiation and hydrolytic stability of a magnesium-potassium phosphate (MPP) matrix, are presented, which is being developed for the purpose of immobilizing 14C, a product of processing mixed uranium-plutoniu