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| Issue |
Title |
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| Vol 15, No 5 (2024) |
Design-Experimental Method for Determination of Thermocouple Inertia within the Pre-Reactor Tests of Fuel Rods Samples |
Abstract
PDF (Rus)
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S. E. Arefinkina, A. N. Abramov, A. V. Babenko, A. D. Gerstle, N. A. Dmitrieva, D. Yu. Erak, P. K. Efremov, O. V. Mikhin, Yu. B. Nichiporenko, V. V. Yakovlev |
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| Vol 15, No 5 (2024) |
The Use of Erbium as a Burnable Absorber in VVER-Type Reactors in a Closed Fuel Cycle |
Abstract
PDF (Rus)
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A. R. Muzafarov, V. I. Savander |
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| Vol 14, No 1 (2023) |
Hydrogen Solubility in Zirconium Alloys E110opt and E635 |
Abstract
PDF (Rus)
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A. A. Plyasov, A. V. Fedotov, N. S. Saburov, E. N. Mikheev, A. V. Tenishev, M. G. Isaenkova, V. V. Mikhalchik |
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| Vol 12, No 1 (2021) |
Effect of External Induced Convection on Heat Transfer during Boiling of Water |
Abstract
PDF (Rus)
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Soufiane Laouar, Nihat Yanar, Yu. E. Litvintsova, D. M. Kuzmenkov, M. I. Delov, K. V. Kutsenko |
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| Vol 14, No 5 (2023) |
Irradiation-Induced Creep and Re-Sintering of Large Grain Sized UO2 Fuel |
Abstract
PDF (Rus)
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E. N. Mikheev, A. V. Fedotov, N. M. Rysev, V. V. Novikov, O. A. Bakhteev, A. L. Izhutov, A. V. Burukin, S. V. Seredkin, G. A. Ilyinykh |
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| Vol 11, No 6 (2020) |
Development of a One-Dimensional Thermal-Hydraulics Model Intended for Studying Stability of a Reactor with a Supercritical Steam Coolant |
Abstract
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A. M. Sujyan, V. S. Kharitonov, A. A. Frolov |
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| Vol 11, No 6 (2020) |
Coupled Thermal-Hydraulic and Neutron-Physical Calculation of IR-8 Reactor’s Fuel Assembly Using MCU-PTR/ATHLET Codes |
Abstract
PDF (Rus)
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K. I. Glyva, S. P. Nikonov, Y. E. Pesnya, V. V. Trofimchuk |
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| Vol 11, No 6 (2020) |
Development of Models of the Core of a Lead-Cooled Reactor in the Athlet Code |
Abstract
PDF (Rus)
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V. A. Chudinova, S. P. Nikonov |
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| Vol 13, No 2 (2022) |
Two-Stage Technique of Controlling the Heat Release Distribution |
Abstract
PDF (Rus)
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А. М. Kuzmin |
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