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Background <p>To close the nuclear fuel cycle, the state program for the development of nuclear power industry in the Russian Federation assumes the development of new radiochemical production facilities and technologies. The most important task is to justify fire, explosion, nuclear, and radiation safety, as well as to minimize the risk of accidents at newly developed radiochemical facilities for nuclear fuel production and reprocessing of spent nuclear fuel (SNF). However, verified and certified codes for predicting processes in the non-reactor part of the fuel cycle are actually unavailable.</p> Aim <p>To develop a&#xa0;system of mathematical models and codes substantiating safety of radiochemical technologies in the production of nuclear fuel and reprocessing of SNF; to test the operability of the codes, their system, and proposed approach.</p> Materials and methods <p>A&#xa0;calculated assessment of fire, explosion, nuclear, and radiation safety of radiochemical production processes and equipment was carried out using a&#xa0;system of mathematical models and codes providing the necessary overall operability. The assessment method includes calculation of chemical and isotopic composition of fuel, determination of process characteristics, simulation of fluid dynamics processes, as well as calculation of critical characteristics and intensity of radiation fields, explosion and fire hazard indicators.</p> Results <p>Requirements for mathematical models are defined. An approach to the calculation safety assessment is proposed based on end-to-end calculations using a&#xa0;system of mathematical models and codes. The effectiveness of the developed system for analyzing emergency scenarios and assessing safety criteria for technological solutions is demonstrated. The dose load of the extractant and release of radiolytic hydrogen in dissolution and fractionation operations are assessed.</p> Conclusion <p>The operability of both individual codes and proposed approach to the calculated safety assessment as a&#xa0;whole is confirmed. A&#xa0;system of mathematical models and codes should be developed and verified for subsequent application in safety substantiation of radiochemical production facilities. The proposed system of models and codes will significantly reduce the time and costs of experimental substantiation.</p>

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System of models and codes for substantiating the safety of radiochemical technologies: a review

  • 期刊论文

  • 发表日期：

    2025年9月1日

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  • Inga R. Makeyeva,
  • Nikita D. Dyrda,
  • Igor V. Peshkichev,
  • Olga V. Shmidt

摘要

Background

To close the nuclear fuel cycle, the state program for the development of nuclear power industry in the Russian Federation assumes the development of new radiochemical production facilities and technologies. The most important task is to justify fire, explosion, nuclear, and radiation safety, as well as to minimize the risk of accidents at newly developed radiochemical facilities for nuclear fuel production and reprocessing of spent nuclear fuel (SNF). However, verified and certified codes for predicting processes in the non-reactor part of the fuel cycle are actually unavailable.

Aim

To develop a system of mathematical models and codes substantiating safety of radiochemical technologies in the production of nuclear fuel and reprocessing of SNF; to test the operability of the codes, their system, and proposed approach.

Materials and methods

A calculated assessment of fire, explosion, nuclear, and radiation safety of radiochemical production processes and equipment was carried out using a system of mathematical models and codes providing the necessary overall operability. The assessment method includes calculation of chemical and isotopic composition of fuel, determination of process characteristics, simulation of fluid dynamics processes, as well as calculation of critical characteristics and intensity of radiation fields, explosion and fire hazard indicators.

Results

Requirements for mathematical models are defined. An approach to the calculation safety assessment is proposed based on end-to-end calculations using a system of mathematical models and codes. The effectiveness of the developed system for analyzing emergency scenarios and assessing safety criteria for technological solutions is demonstrated. The dose load of the extractant and release of radiolytic hydrogen in dissolution and fractionation operations are assessed.

Conclusion

The operability of both individual codes and proposed approach to the calculated safety assessment as a whole is confirmed. A system of mathematical models and codes should be developed and verified for subsequent application in safety substantiation of radiochemical production facilities. The proposed system of models and codes will significantly reduce the time and costs of experimental substantiation.