Current status of the BN-1200M project: a review.

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Title: Current status of the BN-1200M project: a review.
Authors: Vasyaev, A. V.1 (AUTHOR), Kerekesha, A. V.1 (AUTHOR), Kryukov, A. N.1 (AUTHOR), Marova, E. V.1 (AUTHOR) marova@okbm.nnov.ru, Shepelev, S. F.1 (AUTHOR), Andreev, A. V.2 (AUTHOR), Dyagilev, A. M.2 (AUTHOR), Egorov, S. V.2 (AUTHOR), Yashkin, A. V.2 (AUTHOR)
Source: Atomic Energy. Jul2025, Vol. 138 Issue 3, p121-132. 12p.
Subjects: Nuclear energy, Fast reactors, System safety, Fuel cycle, Sodium cooled reactors, Industrial development projects, Engineering design
Geographic Terms: Russia
Abstract: Background: Development of a two-component nuclear power system with a closed nuclear fuel cycle based on new-generation fast reactors represents an important task put forward in the Strategy for the Development of Nuclear Power in the Russian Federation until 2050. Aim: To generalize the results of developments for the project of a new generation commercial power unit with a BN-1200M reactor and to substantiate innovative engineering solutions for its equipment and systems. Materials and methods: The BN-1200M project uses both reference engineering solutions that have proven themselves well during the operation of BN-600 and BN-800 power units and advanced solutions for the core, main circulation pumps, steam generator, cold traps, reloading system, and layout of the primary and secondary circuit equipment. The current work is focused on the justification of mixed uranium-plutonium fuel, design of the emergency heat removal system, operational safety, manufacturing technology for structural elements of a two-module vessel steam generator, new structural materials, etc. Results: An engineering design for a sodium-cooled BN-1200M fast neutron reactor has been developed; the competitiveness of the project has been substantiated; design materials for the power unit have been developed. The results of R&D on selecting emergency core protection using passive equipment in the emergency heat removal system for natural circulation along the circuits and justifying new structural materials in heat exchange equipment have increased the level of safety, reliability, and cost-effectiveness of the BN-1200M reactor as compared to previous projects and promising energy sources. Conclusion: The completed work became a transition to the commercial development of the designed power unit with a high-power BN-1200M reactor plant in a two-component nuclear power system. This stage of commercial development solves the urgent task of completing the experimental validation of engineering solutions for equipment, including the development and testing of prototypes on sodium benches. [ABSTRACT FROM AUTHOR]
Copyright of Atomic Energy is the property of Springer Nature and its content may not be copied or emailed to multiple sites without the copyright holder's express written permission. Additionally, content may not be used with any artificial intelligence tools or machine learning technologies. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
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  Data: Current status of the BN-1200M project: a review.
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  Data: Background: Development of a two-component nuclear power system with a closed nuclear fuel cycle based on new-generation fast reactors represents an important task put forward in the Strategy for the Development of Nuclear Power in the Russian Federation until 2050. Aim: To generalize the results of developments for the project of a new generation commercial power unit with a BN-1200M reactor and to substantiate innovative engineering solutions for its equipment and systems. Materials and methods: The BN-1200M project uses both reference engineering solutions that have proven themselves well during the operation of BN-600 and BN-800 power units and advanced solutions for the core, main circulation pumps, steam generator, cold traps, reloading system, and layout of the primary and secondary circuit equipment. The current work is focused on the justification of mixed uranium-plutonium fuel, design of the emergency heat removal system, operational safety, manufacturing technology for structural elements of a two-module vessel steam generator, new structural materials, etc. Results: An engineering design for a sodium-cooled BN-1200M fast neutron reactor has been developed; the competitiveness of the project has been substantiated; design materials for the power unit have been developed. The results of R&D on selecting emergency core protection using passive equipment in the emergency heat removal system for natural circulation along the circuits and justifying new structural materials in heat exchange equipment have increased the level of safety, reliability, and cost-effectiveness of the BN-1200M reactor as compared to previous projects and promising energy sources. Conclusion: The completed work became a transition to the commercial development of the designed power unit with a high-power BN-1200M reactor plant in a two-component nuclear power system. This stage of commercial development solves the urgent task of completing the experimental validation of engineering solutions for equipment, including the development and testing of prototypes on sodium benches. [ABSTRACT FROM AUTHOR]
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  Data: <i>Copyright of Atomic Energy is the property of Springer Nature and its content may not be copied or emailed to multiple sites without the copyright holder's express written permission. Additionally, content may not be used with any artificial intelligence tools or machine learning technologies. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract.</i> (Copyright applies to all Abstracts.)
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        Value: 10.1007/s10512-025-01236-6
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        Text: English
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      – SubjectFull: Nuclear energy
        Type: general
      – SubjectFull: Fast reactors
        Type: general
      – SubjectFull: System safety
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      – SubjectFull: Fuel cycle
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