Investigation of the Heat-Insulation Properties of the Steam-Water Gap in the Downcomer Pipes of a Steam Generator von Semchenkov, A. A., Novosel’skii, O. Yu, Lemekhov, Yu. V., Khizhnyak, A. G., Shpanskii, S. V., Shishov, V. P.

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Investigation of the development of the 1986 accident at the Chernobyl nuclear power plant von Cherkashov, YuM, Novosel'skii, OYu, Checherov, K P

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Increasing the nominal safety of the no. 5 unit of the Kursk nuclear power plant von Potapov, A A, Panin, V M, Ukharov, S G, Novosel'skii, OYu

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Comprehensive analysis of mechanical and thermohydraulic processes in the graphite masonry of channel rectors during an accidental rupture of a fuel channel von SOLOV'EV, S. L, GABARAEV, B. A, NOVOSEL'SKII, O. Yu, FILINOV, V. N, PARAFILO, L. M, KRYUCHKOV, D. V

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Determining the onset of flow crisis in a multipurpose valve using a 3D thermohydraulic code von Novosel’skii, O. Yu, Skibin, A. P., Solov’ev, S. L., Shishov, A. V.

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Criteria for the fracture of RBMK fuel-channel tubes when accidental overheating occurs von NOVOSEL'SKII, O. YU, FILINOV, V. N

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The application of computational fluid dynamics for determining the hydraulic characteristics of pipelines at nuclear power stations von NOVOSEL'SKII, O. Yu, PETROV, V. E, SKIBIN, A. P, SOLOV'EV, S. L, SHISHOV, A. V

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Investigation of the development of the 1986 accident at the chernobyl nuclear power plant von CHERKASHOV, Yu. M, NOVOSEL'SKII, O. Yu, CHECHEROV, K. P

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Determining the onset of flow crisis in a multipurpose valve using a 3D thermohydraulic code von NOVOSEL'SKII, O. Yu, SKIBIN, A. P, SOLOV'EV, S. L, SHISHOV, A. V

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Increasing the nominal safety of the no. 5 unit of the kursk nuclear power plant von POTAPOV, A. A, PANIN, V. M, UKHAROV, S. G, NOVOSEL'SKII, O. Yu

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Assessment of the Vulnerability of RBMK Fuel Channels to Loads Produced by the Rupturing of One Channel von Gabaraev, B A, Novosel'skii, O Yu, Filinov, V N, Parafilo, L M

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Separation system of a new-generation boiling-water vessel reactor von Karasev, V. B., Novosel’skii, O. Yu, Shishov, A. V.

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Methodological questions concerning investigations of the hydraulic characteristics of the water-leveling pipes of the separator drums in a RBMK reactor von Karasev, V. B., Novosel’skii, O. Yu, Smolin, V. N., Shishov, A. V.

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Investigation of the hydraulic characteristics of the water-leveling pipes of RBMK-1000 separator drums von Esikov, V. I., Karasev, V. B., Novosel’skii, O. Yu, Smolin, V. N., Shishov, A. V., Gal’berg, V. P., Stasenko, V. V., Ustinov, E. D.

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Assessment of the vulnerability of RBMK fuel channels to loads produced by the rupturing of one channel von GABARAEV, B. A, NOVOSEL'SKII, O. Yu, FILINOV, V. N, PARAFILO, L. M

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Investigation of the behavior of the technological channels of a RBMK reactor under conditions of heating during an accident von Novosel'skii, O. Yu, Filinov, V. N., Kryuchkov, I. I.

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Effect of nonsimultaneous rupture of the technological channels on the dynamics of pressure in the reactor space of a RBMK unit von Gabaraev, B. A., Novosel'skii, O. Yu, Safonov, V. K., Simonov, S. L.

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Testing the VSPLESK program with data of experiments made on a model of an accident localization system von Karasev, V. B., Novosel'skii, O. Yu, Safonov, V. K., Murashko, A. N., Isaev, O. A.

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Hydraulic resistance of channels with permeable walls von Kochenov, I. S., Novosel'skii, O. Yu

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Hydrostatic calculation of a nuclear reactor cooling system von Kochenov, I. S., Novosel'skii, O. Yu

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