Verification of PULSAR+software von Tutnov, An. A., Tutnov, Al. A., Alekseev, E. E.

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PULSAR+ : A program for calculating the behavior of fuel elements in a nuclear fuel assembly in accidents with coolant losses and reactivity spikes von TUTNOV, A. A, ALEKSEEV, E. E

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Comparison of experimental data and PULSAR-2 calculations for different fuel assemblies and reactors von Tutnov, An. A., Tutnov, Al. A., Dubrovin, K. P., Ul'yanov, A. I.

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Computational and experimental investigation of fretting corrosion and vibrations of VVÉR-1000 fuel assemblies von Drozdov, Yu. N., Tutnov, A. A., Tutnov, An. A., Alekseev, E. E., Makarov, V. V., Afanas’ev, A. V.

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A calculated basis for the strength and failureprobability of VVÉR contaiment von Tutnov, A. A., Tutnov, An. A., Kiselev, A. S., Kiselev, Al. S., Loskutov, O. D., Danichev, V. V., Ul'yanov, A. I.

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Pulsar-2: Mathematical modeling of thermophysical and thermomechanical processes in the fuel elements von Tutnov, An. A., Tutnov, A. A., Ul’yanov, A. I.

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Modeling unsteady vapor condensation by rapid expansion von KUDRYASHOV, N. A, TUTNOV, A. A

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Computational-experimental studies of fretting corrosion and oscillations of the fuel bundles of the VVER-1000 power reactor von Drozdov, Yu. N., Tutnov, A. A., Tutnov, An. A., Alekseev, E. E., Makarov, V. V., Afanas’ev, A. V.

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Computational and experimental investigation of fretting corrosion and vibrations of VVÉR-1000 fuel assemblies von DROZDOV, Yu. N, TUTNOV, A. A, TUTNOV, An. A, ALEKSEEV, E. E, MAKAROV, V. V, AFANAS'EV, A. V

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Methods and results of an analysis of the nonlinear thermomechanics of crack development in a reactor vessel during accidents von Tutnov, A. A., Kiselev, A. S., Tutnov, An. A., Loskutov, O. D., Ul'yanov, A. I.

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A calculated basis for the strength and failure probability of VVÉR containment von TUTNOV, A. A, TUTNOV, An. A, KISELEV, A. S, KISELEV, Al. S, LOSKUTOV, O. D, DANICHEV, V. V, UL'YANOV, A. I

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An approach to the probabilistic justification of a leak before break concept and break elimination for VVER secondary circuit pipelines von Alekseev, A. T., Alekseev, P. V., Loskutov, O. D., Tutnov, A. A.

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Method of Integral Reliability Assessment of Equipment and Personnel of Long-Operating NPP Power Unit von Sobolev, A. V., Tutnov, I. A., Tsarev, V. S., Ukraintsev, V. F.

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Assessment of the personnel reliability indicators during long-term operation of a nuclear power plant unit von Sobolev, Artem V., Tutnov, Igor A., Ukraintsev, Vladimir F.

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QUALITY AND RELIABILITY OF LOW-POWER POWER SYSTEMS von Boykova, T.V., Grigoriev, A.S., Makolkin, D.V., Korolev, S.A., Tutnov, I.A.

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The method of research nuclear installation conversion at the decommissioning stage von Baidarov, D. Yu, Boykova, T. V., Kochnov, Yu. O., Safronova, N. N., Tutnov, I. A.

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Numerical Modeling of RBMK-1000 Graphite Stack Distortion von Tutnov, A. A., Kiselev, A. S., Krut’ko, E. S.

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Fracture of the Alloy E-110 in Different Loading Regimes von Dorovskoi, V. M., Tutnov, I. A.

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Determination of Effective Temperature at in-pile Study of Nuclear Fuel von Belendryasova, E G, Panasenko, R A, Tutnov, I A, Anufriev, B F, Maksimkin, A I

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Perspectives and principles of formulation of legal basis of diagnostic quality control of materials and products of nanostructure composites von Baryshev, Gennady K., Tutnov, Igor A., Biryukov, Aleksandr P.

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