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Neutron Physics Experiments at the BIGR and BIR-2M Pulsed Reactors
Vorontsov S., Kuvshinov M., Sibgatullin I.
Comprehensive Experiments on Subcritical Assemblies of Cascade Reactor Systems
Zavyalov N., Il’kaev R., Kolesov V., Ivanin I., Zhitnik A., Kuvshinov M., Nefedov Y., Punin V., Tel’nov A., Khoruzhi V.
Parameters of a Pulsed Reactor for Pumping a Large-Size NPL
Kolesov V., Khoruzhy V., Grechushkin V., Pikulev A.
Measurement of prompt neutron generation time at the VIR-2M pulsed nuclear reactor
Glukhov L., Kotkov S., Kuznetsov M., Chursin S.
Planned Destruction of Metal-Core Reactor: Simulation of Catastrophic Accidents and New Experimental Possibilities
Vorontsov S., Kuvshinov M., Narozhnyi A., Popov V., Solov’ev V., Yuferev V.
On the Effect of Reactor Irradiation on Mo and W Interdiffusion
Churin V., Ivanov A.
Development of Software-Controlled Systems for Monitoring Physical Parameters of Nuclear Research Reactor Radiation
Pikulina G., Ovchinnikov M., Yukhnevich V., Koshelev A., Drozdov Y., Raspopov N., Majornikov V., Pickorskiy I.
Methodology of Calculation of Hypothetical Isomeric γ-Reactors by the Example of 178m2Hf
Kolesov V., Abramovich S., Shmarov A., Intjapina E.
Experimental Determination of the Effective Resonance Absorption Integrals of 238U and 158Gd in Urania–Gadolinia Rods
Stogov Y., Prosyolkov V.
The influence of changes in the VVER-1000 fuel assembly shape during operation on the power density distribution
Shishkov L., Gorodkov S., Mikailov E., Sukhino-Homenko E., Sumarokova A.
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., Pavlov S., Urtenov D., Ustinov V.
Use of Neptunium-containing Fuel in Lead-cooled Fast Reactor
Apse V., Shmelev A., Kulikov G., Kulikov E.
BIGR Reactor
Mamaev D., Kolesov V., Kuvshinov M., Pichugin A.
Engineering Margin Factors Used in the Design of the VVER Fuel Cycles
Lizorkin M., Shishkov L.
Advantages of Production of New Fissionable Nuclides for the Nuclear Power Industry in Hybrid Fusion-Fission Reactors
Tsibulskiy V., Andrianova E., Davidenko V., Rodionova E., Tsibulskiy S.
On the equilibrium isotopic composition of the thorium–uranium–plutonium fuel cycle
Marshalkin V., Povyshev V.
Optimization Study of the IBR-2 Reactor
Ananiev V., Pepelyshev Y., Rogov A.
Impact of Powerful Thermal and Neutron Fluxes on the Structural Elements of Fusion and Fission Reactors
Chirkov A., Ryzhkov S.
History of Formation and Practical Realization of the Coupled Reactor Concept
Kolesov V.
Simulation of Nuclear Reactor Kinetics by the Monte Carlo Method
Gomin E., Davidenko V., Zinchenko A., Kharchenko I.
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., Kulikov G.
Generalization of two-dimensional DDL schemes of the GQ method for three-dimensional arbitrary hexahedral spatial mesh
Nikolaev A.
Nuclear Power Unit with Molten Salt Fuel for the Arctic
Kovalchuk M., Chaivanov B., Abalin S., Feynberg O.
The 50th Anniversary of the WWR-K Research Reactor
Shaimerdenov A., Nakipov D., Arinkin F., Gizatulin S., Chakrov P., Kenzhin Y.
New Challenges: From Physics to Medicine
Glazkov V., Somenkov V., Kovalenko E., Borisova P.
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