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Background <p>Over the next decade, the Russian Federation is planning to construct a&#xa0;research molten salt reactor. The purpose of this reactor is to demonstrate the feasibility of burning minor actinides with molten salt nuclear fuel. The advancement of innovative nuclear technologies requires the concomitant development of a&#xa0;regulatory framework.</p> Aim <p>To ascertain the principal specific features that must be considered when enhancing approaches for the safety regulation of molten-salt reactors, in order to provide scientific and technical support to Rostechnadzor.</p> Materials and methods <p>The Scientific and Engineering Centre for Nuclear and Radiation Safety analyses international approaches to safety regulation and evaluates the suitability of current federal rules and regulations in the field of atomic energy for the safety regulation of molten-salt reactors (MSRs).</p> Results <p>It has been determined that the use of molten nuclear fuel endows the MSR with specific features in terms of physical barriers to the spread of radioactive substances. Thus, the molten salt nuclear fuel circuit acts as a&#xa0;second physical barrier, similar to fuel rods in solid-fuel reactors. This makes it necessary to determine alternative approaches to establishing and justifying limits for nuclear fuel damage in molten salt reactors. Furthermore, in MSRs, the intermediate circuit for cooling the nuclear fuel serves as a&#xa0;third physical barrier and must meet requirements similar to those established for the primary circuit in solid-fuel reactors. When developing approaches to safety regulation of MSRs, it is necessary to take into account the unique technical solutions implemented in modern designs, such as the possibility of emergency drainage of the fuel circuit and adjustment of the chemical composition of nuclear fuel during operation, taking into account the limitations on the solubility of components in the carrier salt, the high interdependence of the neutron-physical and thermohydraulic characteristics of the MSR, etc.</p> Conclusion <p>The unique technical solutions implemented in MSR designs and the specific physical effects caused by the liquid state of nuclear fuel require principally new regulatory approaches to MSR safety regulation.</p>

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Features of safety regulation of reactors with molten salt nuclear fuel

  • 期刊论文

  • 发表日期：

    2026年5月20日

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  • A. V. Kuryndin,
  • A. M. Kirkin,
  • S. V. Sinegribov,
  • A. O. Smirnov,
  • S. A. Savyolov

摘要

Background

Over the next decade, the Russian Federation is planning to construct a research molten salt reactor. The purpose of this reactor is to demonstrate the feasibility of burning minor actinides with molten salt nuclear fuel. The advancement of innovative nuclear technologies requires the concomitant development of a regulatory framework.

Aim

To ascertain the principal specific features that must be considered when enhancing approaches for the safety regulation of molten-salt reactors, in order to provide scientific and technical support to Rostechnadzor.

Materials and methods

The Scientific and Engineering Centre for Nuclear and Radiation Safety analyses international approaches to safety regulation and evaluates the suitability of current federal rules and regulations in the field of atomic energy for the safety regulation of molten-salt reactors (MSRs).

Results

It has been determined that the use of molten nuclear fuel endows the MSR with specific features in terms of physical barriers to the spread of radioactive substances. Thus, the molten salt nuclear fuel circuit acts as a second physical barrier, similar to fuel rods in solid-fuel reactors. This makes it necessary to determine alternative approaches to establishing and justifying limits for nuclear fuel damage in molten salt reactors. Furthermore, in MSRs, the intermediate circuit for cooling the nuclear fuel serves as a third physical barrier and must meet requirements similar to those established for the primary circuit in solid-fuel reactors. When developing approaches to safety regulation of MSRs, it is necessary to take into account the unique technical solutions implemented in modern designs, such as the possibility of emergency drainage of the fuel circuit and adjustment of the chemical composition of nuclear fuel during operation, taking into account the limitations on the solubility of components in the carrier salt, the high interdependence of the neutron-physical and thermohydraulic characteristics of the MSR, etc.

Conclusion

The unique technical solutions implemented in MSR designs and the specific physical effects caused by the liquid state of nuclear fuel require principally new regulatory approaches to MSR safety regulation.