Search Results - "Asmolov, V.G."

New generation first-of-the kind unit – VVER-1200 design features by Asmolov, V.G., Gusev, I.N., Kazanskiy, V.R., Povarov, V.P., Statsura, D.B.

“…The paper is concerned with the commissioning of the new generation NPP-2006 power unit with the VVER-1200 reactor. A comparison is made between the…”
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On a Strategy for the Development of Nuclear Power in Russia by Alekseev, P. N., Gagarinskii, A. Yu, Kalugin, M. A., Kukharkin, N. E., Semchenkov, Yu. M, Sidorenko, V. A., Subbotin, S. A., Teplov, P. S., Fomichenko, P. A., Asmolov, V. G.

“…The objectives of the development of reactor technologies for transitioning to two-component nuclear power with thermal and fast reactors as well as the issues…”
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Service Life Restoration Technology for RBMK: Design, Implementation, and Assimilation Experience by Adamov, E. O., Dragunov, Yu. G., Slobodchikov, A. V., Mikhailov, M. N., Petrov, A. A., Ukharov, S. G., Burlakov, E. V., Asmolov, V. G., Chernikov, O. G., Bystrikov, A. A., Kudryavtsev, K. G., Lozhnikov, I. N., Kharakhnin, S. N.

“…The RBMK design-stage service life was assumed to be 30 years. Ten power-generating units have now exceeded this limit. Service life extension of nuclear power…”
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Main results of study on the interaction between the corium melt and steel in the VVER-1000 reactor vessel during a severe accident performed under the MASCA project by Asmolov, V. G., Zagryazkin, V. N., Tsurikov, D. F., Vishnevsky, V. Yu, D’yakov, Ye. K., Kotov, A. Yu, Repnikov, V. M.

“…The interactions that take place in the corium melt in the reactor vessel in the case of a severe accident at a nuclear power plant were investigated in…”
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On a nuclear power strategy of Russia to 2050 by Alekseev, P. N., Asmolov, V. G., Gagarinskii, A. Yu, Kukharkin, N. E., Semchenkov, Yu. M., Sidorenko, V. A., Subbotin, S. A., Tsibulskii, V. F., Shtrombakh, Ya. I.

“…Relying on fundamental and applied research performed at the National Research Center Kurchatov Institute, historical experience, and modern mathematical…”
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30th anniversary of VVER-1000 startup by Asmolov, V. G., Semchenkov, Yu. M., Sidorenko, V. A.

“…The first power-generating unit with VVER-1000 was brought on line at the Novovoronezh nuclear power plant on May 30, 1980. The history of VVER-1000…”
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The interaction of nuclear reactor core melt with oxide sacrificial material of localization device for a nuclear power plant with water-moderated water-cooled power reactor by Asmolov, V. G., Sulatskii, A. A., Beshta, S. V., Granovskii, V. S., Khabenskii, V. B., Krushinov, E. V., Vitol’, S. A., Al’myashev, V. I., Gusarov, V. V., Strizhov, V. F.

“…The basic results are given of an experimental investigation of the interaction oxide corium melt containing unoxidized zirconium with the sacrificial material…”
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Corium kinematic viscosity measurement by Abalin, S.S., Asmolov, V.G., Daragan, V.D., D’yakov, E.K., Merzlyakov, A.V., Vishnevsky, V.Yu

“…Viscosity is one of the important properties which along with thermal conductivity and coefficient of volumetric expansion, determines convection in molten…”
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Development of the methodology and approaches to validate safety and accident management by Asmolov, V.G.

“…The article compares the development of the methodology and approaches to validate the nuclear power plant safety and accident management in Russia and…”
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Results of investigations of severe accidents involving water-cooled reactors by Asmolov, V. G.

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Increasing the safety of atomic power stations with RBMK reactors by Adamov, E. O., Asmolov, V. G., Vasilevskii, V. P., Egorov, Yu. A., Kalugin, A. K., Nikitin, Yu. M., Nikolaev, V. A., Podlazov, L. N., Sirotkin, A. P., Stenbok, I. A., Cherkashov, Yu. M.

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