81 - 100 toradh á dtaispeáint as 193 toradh san iomlán ar an gcuardach '"Глобальная ядерная безопасность"', am iarratais: 0.26s Beachtaigh na torthaí
  1. 81
    Ways of Energy Supply in the Republic of Armenia

    Ways of Energy Supply in the Republic of Armenia de réir M. T. Hakobyan, A. I. Ksenofontov

    Foilsithe / Cruthaithe 2022-08-01
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  2. 82
    Computational and experimental substantiation of the operability of seals of localizing safety system elements of power units with VVER

    Computational and experimental substantiation of the operability of seals of localizing safety system elements of power units with VVER de réir S. B. Kravets, S. A. Kuzin, V. M. Sapelnikov, S. E. Sinelshchikova, A. A. Povolotska, V. G. Beketov

    Foilsithe / Cruthaithe 2024-07-01
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  3. 83
    Assessment of Stress-strain State of NPP Pipeline Metal Parts and Elements

    Assessment of Stress-strain State of NPP Pipeline Metal Parts and Elements de réir A. K. Adamenkov, I. N. Veselova

    Foilsithe / Cruthaithe 2022-08-01
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  4. 84
    Radical Islamism Hazards in Issues of Safety of Nuclear Industry Facility Construction and Operation

    Radical Islamism Hazards in Issues of Safety of Nuclear Industry Facility Construction and Operation de réir A. N. Nedorubov, N. I. Lobkovskaya

    Foilsithe / Cruthaithe 2022-08-01
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  5. 85
    Priorities of innovative project activities in the Russian fuel and energy sector

    Priorities of innovative project activities in the Russian fuel and energy sector de réir N. K. Savelieva, A. A. Sozinova, O. V. Fokina

    Foilsithe / Cruthaithe 2024-09-01
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  6. 86
    Methods and means of ensuring the accuracy of bending deformation measurements of connecting pipe between the VVER reactor and the steam generator in the conditions of a fuel campaign

    Methods and means of ensuring the accuracy of bending deformation measurements of connecting pipe between the VVER reactor and the steam generator in the conditions of a fuel cam... de réir Yu. V. Krasnikov, V. P. Povarov, A. M. Stepanov, S. G. Fish

    Foilsithe / Cruthaithe 2024-07-01
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  7. 87
    Safety Culture Education and Training in the Republic of Belarus

    Safety Culture Education and Training in the Republic of Belarus de réir T. N. Korbut, A. V. Kuzmin, O. A. Nautsyk, D. A. Kuzmuk

    Foilsithe / Cruthaithe 2022-12-01
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  8. 88
    Study of causes and possible solutions to the problem of specialist shortage in the Russian energy industry with the involvement of HR-branding

    Study of causes and possible solutions to the problem of specialist shortage in the Russian energy industry with the involvement of HR-branding de réir V. A. Bondarenko, T. S. Popova, A. A. Popov

    Foilsithe / Cruthaithe 2023-10-01
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  9. 89
    Assessment of technogenic acoustic background influence on y-spectrometer readings at registration of y-radiation spectra

    Assessment of technogenic acoustic background influence on y-spectrometer readings at registration of y-radiation spectra de réir A. P. Elokhin, S. E. Ulin, A. I. Majidov, A. E. Shustov

    Foilsithe / Cruthaithe 2024-04-01
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  10. 90
    Concept of Creating an Integrated Automated Thermal Imaging Control System

    Concept of Creating an Integrated Automated Thermal Imaging Control System de réir D. V. Shvets, E. A. Abidova, M. V. Kalashnikov, P. V. Povarov, E. V. Vorobev

    Foilsithe / Cruthaithe 2022-08-01
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  11. 91
    MTIR-SCP nuclear safety concept

    MTIR-SCP nuclear safety concept de réir A. S. Lapin, V. Y. Blandinsky, V. A. Nevinitsa, P. A. Fomichenko, Yu. N. Volkov

    Foilsithe / Cruthaithe 2024-07-01
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  12. 92
    Culture and Ethics of Communication in the Distance Educational Process when Training Nuclear Specialists

    Culture and Ethics of Communication in the Distance Educational Process when Training Nuclear Specialists de réir L. V. Zakharova, I. V. Zarochintseva, Y. A. Lupinogina, O. A. Kikinchuk

    Foilsithe / Cruthaithe 2022-08-01
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  13. 93
    Area Contamination Due to Dry Settling and Point Source Stack Effluents Washout by Precipitates

    Area Contamination Due to Dry Settling and Point Source Stack Effluents Washout by Precipitates de réir Oleg A Gubeladze, Avtandil R Gubeladze

    Foilsithe / Cruthaithe 2023-04-01
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  14. 94
    Investigation of the Possibility of Using Secondary Concrete Ouae in the Framework of Additive Technologies

    Investigation of the Possibility of Using Secondary Concrete Ouae in the Framework of Additive Technologies de réir A. R. Davtyan, A. V. Nakhabov

    Foilsithe / Cruthaithe 2022-08-01
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  15. 95
    New data transfer and display system development for NPP safety

    New data transfer and display system development for NPP safety de réir E. V. Vorobiev, G. D. Novoselov, P. V. Povarov, L. V. Tsykhler, A. Yu. Zlobin

    Foilsithe / Cruthaithe 2024-09-01
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  16. 96
    Artificial intelligence in teaching technical English to nuclear engineering students

    Artificial intelligence in teaching technical English to nuclear engineering students de réir I. V. Zarochintseva, Yu. A. Lupinogina, L. V. Zakharova, O. A. Kikinchuk

    Foilsithe / Cruthaithe 2024-07-01
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  17. 97
    Comparative Analysis of Methods of Axial Profiling of WWER-1200 Fuel Assembly on Model Z49A2 Example

    Comparative Analysis of Methods of Axial Profiling of WWER-1200 Fuel Assembly on Model Z49A2 Example de réir E. A. Gerdt, R. A. Vnukov

    Foilsithe / Cruthaithe 2022-09-01
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  18. 98
    Providing a High Level of Safety Culture when Exporting Nuclear Power Technologies

    Providing a High Level of Safety Culture when Exporting Nuclear Power Technologies de réir V. A. Rudenko, T. S. Popova, Yu. A. Evdoshkina

    Foilsithe / Cruthaithe 2022-08-01
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  19. 99
    Modernisation of rotor hydraulic lift pump of steam turbine unit K-1200-6.8/50

    Modernisation of rotor hydraulic lift pump of steam turbine unit K-1200-6.8/50 de réir V. P. Povarov, D. E. Usachev, A. P. Shchukin, V. A. Vorotnikov, A. A. Lotarev

    Foilsithe / Cruthaithe 2024-09-01
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  20. 100
    Analysis and Optimization of Three-Beam Traverse Structure Elements for Reactor Cavity Reinforced Concrete Block Installation

    Analysis and Optimization of Three-Beam Traverse Structure Elements for Reactor Cavity Reinforced Concrete Block Installation de réir S. A. Tomilin, R. V. Pirozhkov, E. A. Tsvelik, E. V. Pinchuk, S. F. Godunov

    Foilsithe / Cruthaithe 2022-08-01
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