Search Results - "MOSEEV, L. I"

Investigation of Fission Product Release from Irradiated Oxide and Nitride Nuclear Fuel on High-Temperature Heating in Helium Flow by Porollo, S. I., Moseev, L. I., Konobeev, Yu. V.

“…The results of an investigation of the release of the radioactive fission products 85 Kr and 137 Cs from dioxide and mononitride nuclear fuel irradiated in the…”
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Fabrication and study of the properties of PuO2−MgO fuel pellets by Kurina, I. S., Moseev, L. I.

“…Defect-free PuO^sub 2^-MgO pellets with a density of 4.4 g/cm^sup 3^ (90% of the computed density of the composition, in which the volume fractions of PuO^sub…”
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Distillation22Na separation from proton-irradiated aluminum targets by Kir'yanov, B. S., Lastov, A. I., Moseev, L. I., Mamonov, A. N., Razbash, A. A., Sevast'yanov, Yu. G.

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Experimental and Computational Investigation of the Emission of Radioactive Products from Irradiated Fuel of Fast Sodium-Cooled Reactor by Zabrodskaya, S. V., Moseev, L. I., Poplavskii, V. M., Porollo, S. I., Tsikunov, A. G., Veremeev, A. M., Osipov, S. L.

“…The key experimental and computational studies of the emission of long-lived radioactive fission products and actinides from uranium dioxide irradiated in…”
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Possibility of Obtaining 10Be from Spent Control Rods from Fast Reactors by Gornov, M G, Gurov, Yu B, Lapushkin, S V, Pechkurov, V A, Pechkurov, A V, Poroshin, N O, Shmelev, A N, Shchurenkova, T D, Moseev, L I, Tarasikov, V P

“…A method is proposed for obtaining ^sup 10^Be from spent fast-reactor control rods. The method is characterized by the fact that it is inexpensive and it can…”
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Production of 10Be isotope from boron carbide irradiated with fast neutrons by Gurov, Yu. B., Ermakov, A. I., Moseev, L. I., Lapushkin, S. V., Novgorodov, A. F., Porollo, S. I., Tarasikov, V. P., Chernyshev, B. A., Filosofov, D. V.

“…A method for producing 10 Be isotope from spent rods of the emergency protection and compensation systems of a fast neutron reactor is described. This isotope…”
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Release of fission products from the reactor fuel of the bilibinsk nuclear power plant under conditions which simulate a severe accident by Baranaev, Yu. D., Viktorov, A. N., Dolgov, V. V., Moseev, L. I.

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Investigation of uranium monocarbide fuel elements in the fuel bundles of the Br-5 reactor by Ibragimov, Sh. Sh, Men'shikova, T. S., Ladygin, A. Ya, Aleksandrov, Yu. I., Likhachev, Yu. I., Galkov, V. T., Vorob'ev, A. N., Moseev, L. I.

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Fabrication and study of the properties of PuO2-MgO fuel pellets by KURINA, I. S, MOSEEV, L. I

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Distillation 22Na separation from proton-irradiated aluminum targets by KIR'YANOV, B. S, LASTOV, A. I, MOSEEV, L. I, MAMONOV, A. N, RAZBASH, A. A, SEVAST'YANOV, Yu. G

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Fabrication and study of the properties of PuO sub(2)-MgO fuel pellets by Kurina, I S, Moseev, LI

“…Defect-free PuO sub(2)-MgO pellets with a density of 4.4 g/cm super(3) (90% of the computed density of the composition, in which the volume fractions of PuO…”
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Possibility of obtaining 10Be from spent control rods from fast reactors by GORNOV, M. G, GUROV, Yu. B, LAPUSHKIN, S. V, PECHKUROV, V. A, PECHKUROV, A. V, POROSHIN, N. O, SHMELEV, A. N, SHCHURENKOVA, T. D, MOSEEV, L. I, TARASIKOV, V. P

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Distillation super(22)Na separation from proton-irradiated aluminum targets by Kir'yanov, B S, Lastov, AI, Moseev, LI, Mamonov, AN, Razbash, A A, Sevast'yanov, YuG

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Gas-chromatographic examination of the accumulation of3H,85Kr, and133Xe in the protective gas, sodium coolant, and constructional materials of the BR-10 by Moseev, L. I., Aristarkov, N. N., Efimov, I. A., Piskunov, V. N., Smolyakov, V. I., Shkuro, S. I.

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