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Background <p>A&#xa0;molten salt nuclear reactor used for burning minor actinides from spent fuel assemblies of power reactors represents a&#xa0;promising way to close the nuclear fuel cycle. For testing a&#xa0;molten salt technology, a&#xa0;molten salt research reactor (MSRR) should be designed and constructed.</p> Aim <p>To define the engineering and physical design of the MSRR, including key technologies of molten salt reactor burners; to develop a&#xa0;safety concept of the molten salt reactor.</p> Materials and methods <p>The present study solves engineering, design, and scientific issues including MSRR design and its neutron-physical and thermal-hydraulic characteristics, selection and justification of construction materials, integrated technology of the operation process, safety concept, etc.</p> Results <p>The preliminary engineering and physical design of the reactor, equipment, and heat removal circuits, including emergency ones, is developed and presented. Main technical characteristics of the reactor involve 10 MW thermal power, 73LiF-27BeF<sub>2</sub> + (PuF<sub>3</sub> + AnF<sub>m</sub>) fuel salt, 141.6 kg/s salt flow rate in the fuel circuit, 664 and 700 °C salt temperature at the reactor inlet and outlet, respectively, and chromium-nickel alloys as candidate structural materials for the reactor equipment. Calculation justifications are performed to adopt MSRR fundamental design and schematic solutions; the parameters obtained earlier are optimized.</p> Conclusion <p>The operating MSRR can be effective to test technological solutions for the development of an industrial high-power 2200–2400 MW(t) molten salt nuclear reactor for burning long-lived minor actinides. The obtained results confirm the feasibility of the design requirements for the MSRR and the possibility of its construction.</p>

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Engineering and physical design of a molten salt research reactor

  • 期刊论文

  • 发表日期：

    2025年9月18日

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  • A. V. Goryachikh,
  • I. V. Zayko,
  • D. S. Klimenko,
  • I. A. Larionov,
  • A. A. Semchenkov,
  • D. A. Ognerubov,
  • N. V. Romanova,
  • I. T. Tretyakov,
  • A. V. Lopatkin

摘要

Background

A molten salt nuclear reactor used for burning minor actinides from spent fuel assemblies of power reactors represents a promising way to close the nuclear fuel cycle. For testing a molten salt technology, a molten salt research reactor (MSRR) should be designed and constructed.

Aim

To define the engineering and physical design of the MSRR, including key technologies of molten salt reactor burners; to develop a safety concept of the molten salt reactor.

Materials and methods

The present study solves engineering, design, and scientific issues including MSRR design and its neutron-physical and thermal-hydraulic characteristics, selection and justification of construction materials, integrated technology of the operation process, safety concept, etc.

Results

The preliminary engineering and physical design of the reactor, equipment, and heat removal circuits, including emergency ones, is developed and presented. Main technical characteristics of the reactor involve 10 MW thermal power, 73LiF-27BeF2 + (PuF3 + AnFm) fuel salt, 141.6 kg/s salt flow rate in the fuel circuit, 664 and 700 °C salt temperature at the reactor inlet and outlet, respectively, and chromium-nickel alloys as candidate structural materials for the reactor equipment. Calculation justifications are performed to adopt MSRR fundamental design and schematic solutions; the parameters obtained earlier are optimized.

Conclusion

The operating MSRR can be effective to test technological solutions for the development of an industrial high-power 2200–2400 MW(t) molten salt nuclear reactor for burning long-lived minor actinides. The obtained results confirm the feasibility of the design requirements for the MSRR and the possibility of its construction.