Lead coolant modeling in system thermal-hydraulic code HYDRA-IBRAE/LM and some validation results by Mosunova, N.A., Alipchenkov, V.M., Pribaturin, N.A., Strizhov, V.F., Usov, E.V., Lobanov, P.D., Afremov, D.A., Semchenkov, A.A., Larin, I.A.

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Reactor Pressure Vessel Cooling Scheme: Selection and Validation for Small Nuclear Power Plants by Afremov, D. A., Dragunov, Yu. G., Koretskii, S. A., Kudinov, V. V., Kulikov, D. G.

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Study into the Distribution of Mass Velocity and Enthalpy of Single-Phase and Two-Phase Flows in the Cross Section of a 19-Rod Bundle in an Electrically Heated Model of an RBMK-100... by Afremov, D. A., Basov, A. V., Boltenko, E. A., Davydov, M. V., Emelyanov, A. I., Kononenko, I. V., Stolpnik, A. V.

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The EUCLID/V1 Integrated Code for Safety Assessment of Liquid Metal Cooled Fast Reactors. Part 2: Validation and Verification by Alipchenkov, V. M., Boldyrev, A. V., Veprev, D. P., Zeigarnik, Yu. A., Kolobaeva, P. V., Moiseenko, E. V., Mosunova, N. A., Seleznev, E. F., Strizhov, V. F., Usov, E. V., Osipov, S. L., Gorbunov, V. S., Afremov, D. A., Semchenkov, A. A.

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Fundamentals, current state of the development of, and prospects for further improvement of the new-generation thermal-hydraulic computational HYDRA-IBRAE/LM code for simulation of... by Alipchenkov, V. M., Anfimov, A. M., Afremov, D. A., Gorbunov, V. S., Zeigarnik, Yu. A., Kudryavtsev, A. V., Osipov, S. L., Mosunova, N. A., Strizhov, V. F., Usov, E. V.

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Modeling of Cesium and Iodine Transport in the FAL-ISP 1 Experiment by Afremov, D. A., Zhukov, I. V., Zhuravleva, Yu. V., Pripachkin, D. A.

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Investigation of Processes in Lead Coolant with Loss-of-Integrity of a Heat-Exchange Tube in a Brest-OD-300 Steam Generator by Abramov, A. V., Kovalev, E. O., Kolesnikov, P. A., Mukhametov, R. R., Naumenko, M. Yu, Nikitin, O. A., Petrov, D. V., Stolbikov, M. Yu, Yudov, A. G., Afremov, D. A., Lemekhov, V. V., Tutukin, A. V.

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PUChOK BM-DF Code Verification Based on Experimental Study of the Heat-Exchange Crisis Accompanying Deformation of the Channel Tube of an RBMK Fuel Assembly by Afremov, D. A., Emel’yanov, A. I., Kudryavtsev, A. V., Mironov, Yu. V., Mingaleeva, G. S., Radkevich, V. E., Yashnikov, D. A., Brus, N. A.

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Fourth International Scientific and Technical Conference on Innovative Projects and Technologies of Nuclear Power (MNTK NIKIET-2016) by Dragunov, Yu. G., Gabaraev, B. A., Dzhalavyan, A. V., Lopatkin, A. V., Pimenov, A. O., Strebkov, Yu. S., Lemekhov, V. V., Moiseev, A. V., Cherepnin, Yu. S., Arkhipov, O. P., Evropin, S. V., Ryasnyanskii, S. G., Kulikov, D. G., Afremov, D. A., Danilov, I. V.

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Verification of relap5/mod3.2 critical heat transfer computational method by experiments performed on the ks facility by Afremov, D. A., Yashnikov, D. A.

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