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Neutron Physics Experiments at the BIGR and BIR-2M Pulsed Reactors
Vorontsov S.V., Kuvshinov M.I., Sibgatullin I.Z.
Use of Neptunium-containing Fuel in Lead-cooled Fast Reactor
Apse V.A., Shmelev A.N., Kulikov G.G., Kulikov E.G.
Nuclear Power Unit with Molten Salt Fuel for the Arctic
Kovalchuk M.V., Chaivanov B.B., Abalin S.S., Feynberg O.S.
Evolution of Nuclear Physics Research at IR-8 Reactor
Arzumanov S.S., Govor L.I., Demidov A.M.
A setup for active neutron analysis of the fissile material content in fuel assemblies of nuclear reactors
Bushuev A.V., Kozhin A.F., Aleeva T.B., Zubarev V.N., Petrova E.V., Smirnov V.E.
Methodology of Calculation of Hypothetical Isomeric γ-Reactors by the Example of 178m2Hf
Kolesov V.F., Abramovich S.N., Shmarov A.E., Intjapina E.V.
On the equilibrium isotopic composition of the thorium–uranium–plutonium fuel cycle
Marshalkin V.Y., Povyshev V.M.
Impact of Powerful Thermal and Neutron Fluxes on the Structural Elements of Fusion and Fission Reactors
Chirkov A.Y., Ryzhkov S.V.
Simulation of Nuclear Reactor Kinetics by the Monte Carlo Method
Gomin E.A., Davidenko V.D., Zinchenko A.S., Kharchenko I.K.
Calculation of Prompt Fission Neutron Lifetimes by the Monte Carlo Method
Gomin E.A., Davidenko V.D., Zinchenko A.S., Kharchenko I.K.
Advantages of Production of New Fissionable Nuclides for the Nuclear Power Industry in Hybrid Fusion-Fission Reactors
Tsibulskiy V.F., Andrianova E.A., Davidenko V.D., Rodionova E.V., Tsibulskiy S.V.
Development of Software-Controlled Systems for Monitoring Physical Parameters of Nuclear Research Reactor Radiation
Pikulina G.N., Ovchinnikov M.A., Yukhnevich V.A., Koshelev A.S., Drozdov Y.M., Raspopov N.V., Majornikov V.S., Pickorskiy I.M.
Nuclear Power System Based on Fission and Fusion Reactors is the Strategic Line of Nuclear Power Industry Development
Velikhov E.P., Kovalchuk M.V., Ilgisonis V.I., Ignatiev V.V., Tsibulskiy V.F., Andrianova E.A., Blandinskiy V.Y.
1 - 13 of 13 Items

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