Zobrazeno 1 - 7
of 7
pro vyhledávání: '"L. I. Moseev"'
Autor:
A. M. Veremeev, S. I. Porollo, S. V. Zabrodskaya, V. M. Poplavskii, L. I. Moseev, S. L. Osipov, A. G. Tsikunov
Publikováno v:
Atomic Energy. 122:390-395
The key experimental and computational studies of the emission of long-lived radioactive fission products and actinides from uranium dioxide irradiated in BN-600 into sodium and the gas phase in the range 150–800°C, performed on the experimental b
Autor:
L. I. Moseev, V. P. Tarasikov, B. A. Chernyshev, A. F. Novgorodov, D. V. Filosofov, S. I. Porollo, A. I. Ermakov, S. V. Lapushkin, Yu. B. Gurov
Publikováno v:
Instruments and Experimental Techniques. 53:777-782
A method for producing 10Be isotope from spent rods of the emergency protection and compensation systems of a fast neutron reactor is described. This isotope has found application in targets and radioactive beams for experiments at modern heavy-ion a
Autor:
V. A. Pechkurov, M.G. Gornov, T. D. Shchurenkova, A. V. Pechkurov, V. P. Tarasikov, L. I. Moseev, Yu.B. Gurov, A. N. Shmelev, N. O. Poroshin, S. V. Lapushkin
Publikováno v:
Atomic Energy. 89:668-672
A method is proposed for obtaining 10Be from spent fast-reactor control rods. The method is characterized by the fact that it is inexpensive and it can combine the separation of 10Be with the recovery of expensive 10B. The method has been tested on B
Autor:
L. I. Moseev, I. S. Kurina
Publikováno v:
Atomic Energy. 82:347-350
Defect-free PuO2−MgO pellets with a density of 4.4 g/cm3 (90% of the computed density of the composition, in which the volume fractions of PuO2 and MgO equal 15 and 85% respectively), were obtained. Work with plutonium-containing material showed th
Publikováno v:
Atomic Energy. 74:380-384
Autor:
A. N. Vorob'ev, Yu. I. Likhachev, Sh. Sh. Ibragimov, L. I. Moseev, V. T. Galkov, A. Ya. Ladygin, T. S. Men'shikova, Yu. I. Aleksandrov
Publikováno v:
Soviet Atomic Energy. 30:1-5
Publikováno v:
Soviet Atomic Energy. 47:847-849
The tritium level in the sodium coolant in the first loop on the BR-10 attained 6·10−4 Ci/liter, but this fell to 9·10−6 Ci/liter when the oxide trap was working. The second loop accumulates tritium up to 3.5·10−5 Ci/liter with the cold trap