Thermodynamic analysis of uranium–gadolinium fuel stability at high temperatures von Popov, S. G., Proselkov, V. N., Lysenko, V. A.

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VVER-440 fuel cycle improvement: status and prospects von Gagarinskiy, A. A., Lizorkin, M. P., Proselkov, V. N., Solovyeva, E. G., Adeev, V. A.

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Computational investigation of the temperature and geometric characteristics of VVÉR fuel in the Kozlodui nuclear power plant (Bulgaria) under normal operating conditions von PASSAGE, G, STEFANOVA, S, PETKOV, P, SHCHEGLOV, A. S, PROSELKOV, V. N

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Heat Capacity in Two-Phase Regions and Heat of Phase Transformations of Certain Zr-Nb Binary Alloys von Popov, S G, Proselkov, V N

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VVER-440 fuel cycles based on fuel assemblies with larger uranium loads and higher uranium content von Gagarinskii, A. A., Saprykin, V. V., Lizorkin, M. P., Proselkov, V. N.

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Comparison of the results of calculations and post-reactor investigations of VVÉR-1000 fuel elements with burnup 49 MW.days/kg von PASSAGE, G, STEFANOVA, S, SHCHEGLOV, A. S, PROSELKOV, V. N

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Application of a Fuel-Element Energy Release Restoration Module in the ATHLET/BIPR-VVER Complex in Modeling a Control-Rod Ejection Accident in VVER-1000 von Gordienko, P. V., Kotsarev, A. V., Lizorkin, M. P., Proselkov, V. N.

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Analysis of the Possibility of Using Fuel Based on Reclaimed Uranium in VVÉR Reactors von Proselkov, V N, Aleshin, S S, Popov, S G, Sidorenko, V D, Slavyagin, P D, Tataurov, AL, Milovanov, O V, Mikheev, EN, Anan'ev, YuA, Pytkin, YuN, Pimenov, YuV

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Comparison of the results of calculations and post-reactor investigations of VVÉR-1000 fuel elements with burnup 49 MW·days/kg von Passage, G., Stefanova, S., Shcheglov, A. S., Proselkov, V. N.

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Using the Offset-Power Diagram to Monitor the Local Linear Power Density of Fuel Elements in a VVÉR-1000 Core von Aver'yanova, S P, Lunin, G L, Proselkov, V N, Filimonov, P E, Gorokhov, A K, Bogatyr', S M, Medvedev, A V, Povarov, V P

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Evolution of isotopic composition of reprocessed uranium during the multiple recycling in light water reactors with natural uranium feed von Smirnov, A. Yu, Sulaberidze, G. A., Alekseev, P. N., Dudnikov, A. A., Nevinitsa, V. A., Proselkov, V. N., Chibinyaev, A. V.

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Thermodynamic simulation of phase equilibria in the UO2-Gd2O3 system at high temperatures von Popov, S. G., Lysenko, V. A., Proselkov, V. N.

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Influence of ^sup 236^U on the Efficacy of Recycling Regenerated Uranium in VVER Fuel von Dudnikov, A A, Nevinitsa, V A, Proselkov, V N, Sumarokova, A S, Fomichenko, P A, Smirnov, A Yu, Sulaberidze, G A

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Influence of 236U on the Efficacy of Recycling Regenerated Uranium in VVER Fuel von Dudnikov, A. A., Nevinitsa, V. A., Proselkov, V. N., Sumarokova, A. S., Fomichenko, P. A., Smirnov, A. Yu, Sulaberidze, G. A.

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The heat capacity in two-phase regions and the heat of phase transformations of some alloys in Zr-Nb and Zr-Sn systems von Popov, S. G., Proselkov, V. N.

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Simulation of the behavior of fuel elements in a VVER-440 for high burnup (using reactor No.3 of the Kol'skaya nuclear power plant as an example) von SHCHEGLOV, A. S, PROSELKOV, V. N, SMIRNOV, A. V, SMIRNOV, V. P, ANAN'EV, YU. A, TSIBULYA, V. A, KOLOSOVSKII, V. G, PANIN, V. N, PYTKIN, YU. N

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THERMODYNAMIC ANALYSIS OF URANIUM-GADOLINIUM FUEL STABILITY AT HIGH TEMPERATURES von POPOV, S. G, PROSELKOV, V. N, LYSENKO, V. A

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Effects of a central hole in a fuel tablet on the thermophysical characteristics of VVER fuel rods von Proselkov, V. N., Shcheglov, A. S., Uksov, V. I.

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Effect of fuel — Cladding axial asymmetry on nuclear fuel element operation von Shcheglov, A. S., Proselkov, V. N.

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Formation and development of a surface layer in the BBER-440 fuel core von Shcheglov, A. S., Sidorenko, V. D., Proselkov, V. N., Bol'shagin, S. M.

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