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Feasibility of creating a specialized reactimeter based on the inverse solution to kinetics equation with a current-mode neutron detector
Koshelev A.S., Arapov A.V., Ovchinnikov M.A.
The PLM Plasma Device for Tests of Tungsten with Powerful Stationary Heat Plasma Loads
Budaev V.P., Fedorovich S.D., Martynenko Y.V., Lukashevsky M.V., Gubkin M.K., Karpov A.V., Lazukin A.V., Shestakov E.A., Kavyrshin D.I., Rogozin K.S.
Concept of Plasma Heating and Current Drive Neutral Beam System for Fusion Neutron Source DEMO-FNS
Ananyev S.S., Dlougach E.D., Krylov A.I., Kuteev B.V., Panasenkov A.A.
DAREUS Software Package for Modeling the Dynamics of Solution Reactors Using the Monte Carlo Method
Gomin E.A., Davidenko V.D., Davidenko O.V., Kovalishin A.A., Laletin M.N., Pavlov A.K.
Analysis of features of hydrodynamics and heat transfer in the fuel assembly of prospective sodium reactor with a high rate of reproduction in the uranium-plutonium fuel cycle
Lubina A.S., Subbotin A.S., Sedov A.A., Frolov A.A.
On the Effect of Reactor Irradiation on Mo and W Interdiffusion
Churin V.A., Ivanov A.S.
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.
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.
Experimental Determination of the Effective Resonance Absorption Integrals of 238U and 158Gd in Urania–Gadolinia Rods
Stogov Y.V., Prosyolkov V.N.
The influence of changes in the VVER-1000 fuel assembly shape during operation on the power density distribution
Shishkov L.K., Gorodkov S.S., Mikailov E.F., Sukhino-Homenko E.A., Sumarokova A.S.
Estimation of the Possibility of Using the Classical Theory of Nucleation in the Calculation of the Limiting Superheat for a Metastable Liquid in the Region of Onset of Nucleate Boiling
Zhukov Y.M., Pavlov S.Y., Urtenov D.S., Ustinov V.S.
Use of Neptunium-containing Fuel in Lead-cooled Fast Reactor
Apse V.A., Shmelev A.N., Kulikov G.G., Kulikov E.G.
BIGR Reactor
Mamaev D.V., Kolesov V.F., Kuvshinov M.I., Pichugin A.M.
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.
On the equilibrium isotopic composition of the thorium–uranium–plutonium fuel cycle
Marshalkin V.Y., Povyshev V.M.
Optimization Study of the IBR-2 Reactor
Ananiev V.D., Pepelyshev Y.N., Rogov A.D.
Impact of Powerful Thermal and Neutron Fluxes on the Structural Elements of Fusion and Fission Reactors
Chirkov A.Y., Ryzhkov S.V.
History of Formation and Practical Realization of the Coupled Reactor Concept
Kolesov V.F.
Simulation of Nuclear Reactor Kinetics by the Monte Carlo Method
Gomin E.A., Davidenko V.D., Zinchenko A.S., Kharchenko I.K.
On the role of fusion neutron source with thorium blanket in forming the nuclide composition of the nuclear fuel cycle of the Russian Federation
Shmelev A.N., Kulikov G.G.
Generalization of two-dimensional DDL schemes of the GQ method for three-dimensional arbitrary hexahedral spatial mesh
Nikolaev A.A.
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