Skip to main content
Log in

Current state of nuclear fuel cycles in nuclear engineering and trends in their development according to the environmental safety requirements

  • Environmental Protection
  • Published:
Thermal Engineering Aims and scope Submit manuscript

Abstract

The state and trends in the development of nuclear fuel cycles in nuclear engineering, taking into account the ecological aspects of using nuclear power plants, are considered. An analysis of advantages and disadvantages of nuclear engineering, compared with thermal engineering based on organic fuel types, was carried out. Spent nuclear fuel (SNF) reprocessing is an important task in the nuclear industry, since fuel unloaded from modern reactors of any type contains a large amount of radioactive elements that are harmful to the environment. On the other hand, the newly generated isotopes of uranium and plutonium should be reused to fabricate new nuclear fuel. The spent nuclear fuel also includes other types of fission products. Conditions for SNF handling are determined by ecological and economic factors. When choosing a certain handling method, one should assess these factors at all stages of its implementation. There are two main methods of SNF handling: open nuclear fuel cycle, with spent nuclear fuel assemblies (NFAs) that are held in storage facilities with their consequent disposal, and closed nuclear fuel cycle, with separation of uranium and plutonium, their purification from fission products, and use for producing new fuel batches. The development of effective closed fuel cycles using mixed uranium–plutonium fuel can provide a successful development of the nuclear industry only under the conditions of implementation of novel effective technological treatment processes that meet strict requirements of environmental safety and reliability of process equipment being applied. The diversity of technological processes is determined by different types of NFA devices and construction materials being used, as well as by the composition that depends on nuclear fuel components and operational conditions for assemblies in the nuclear power reactor. This work provides an overview of technological processes of SNF treatment and methods of handling of nuclear fuel assemblies. Based on analysis of modern engineering solutions on SNF regeneration, it has been concluded that new reprocessing technologies should meet the ecological safety requirements, provide a more extensive use of the resource base of nuclear engineering, allow the production of valuable and trace elements on an industrial scale, and decrease radioactive waste release.

This is a preview of subscription content, log in via an institution to check access.

Access this article

Price excludes VAT (USA)
Tax calculation will be finalised during checkout.

Instant access to the full article PDF.

Similar content being viewed by others

References

  1. A. D. Trukhnii, Foundations of Contemporary Energetics: A Tutorial for Higher Education Institutes. In 2 vol. Vol. 1: Contemporary Thermalenergetics (Mos. Energ. Inst., Moscow, 2010) [in Russian].

    Google Scholar 

  2. M. A. Skachek, Management with Spent Reactor Fuel and Radioactive Wastes of Power Stations: A Tutorial for Higher Education Institutes (Mos. Energ. Inst., Moscow, 2007) [in Russian].

    Google Scholar 

  3. A. Yu. Gagarinskii, V. M. Novikov, and B. Val’strem, “Social acceptability of power engineering and problems of radioactive wastes,” in Proc. 2nd Annual Conf. Nuclear Soc., Moscow, 1992, pp. 2–8.

    Google Scholar 

  4. A. P. Varnavin, S. E. Vasin, A. I. Vasil’ev, A. V. D’yakov, O. A. Zhukova, A. V. Korolev, N. E. Kukharkin, M. E. Mironenko-Marenkova, L. P. Novikova, V. A. Pavlov, B. S. Stepennov, A. K. Sukhoruchkin, D. B. Stepennov, A. N. Fedoseenkov, E. Yu. Shkuratova, et al., “Technological aspects of management with spent reactor fuel and increase of nuclear and radiation safety at ecological rehabilitation of former coast base in Chervyanaya gulf (Gremikha settlement),” Arktika, Ecology and Economics, No. 3, 4–25 (2013).

    Google Scholar 

  5. R. M. Timerbaev, Russia and Nuclear Non-Proliferation, 1945–1968 (Nauka, Moscow, 1999) [in Russian].

    Google Scholar 

  6. Heat and Atomic Power Stations. A Handbook, Ed. by A. V. Klimenko and V. M. Zorin, (Mos. Energ. Inst., Moscow, 2003) [in Russian], Book 3, 3rd ed.

  7. I. N. Bekman, Radiochemistry: A Tutorial, Vol. 2, Applied Radiochemistry and Radiation Safety (Yurait, Moscow, 2014) [in Russian].

    Google Scholar 

  8. O. M. Saraev, N. N. Oshkanov, A. V. Zrodnikov, V. M. Poplavskii, Yu. M. Ashurko, M. V. Bakanov, B. A. Vasil’ev, Yu. L. Kamanin, V. N. Ershov, M. N. Svyatkin, A. S. Korol’kov, and Yu. M. Krasheninnikov, “Operating experience and prospects for future development of sodium-cooled fast reactors,” Atomic Energy 108, 240–247 (2010).

    Article  Google Scholar 

  9. NP-069-06. Near-Surface Burial of Radioactive Wastes. Safety Requirements (Federal Service on Ecological, Technological and Atomic Control, Moscow, 2006) [in Russian].

  10. F. J. Rahn, A. G. Adamantiades, J. E. Kenton, C. Braun, A Guide to Nuclear Power Technology, Wiley, 1984.

    Google Scholar 

  11. A. G. Goryunov, S. N. Liventsov, and Yu. A. Chursin, Mathematical Simulation of Technological Processes of Water-Extraction Treatment of Nuclear Fuel (Tomsk. Politekhn. Univ., Tomsk, 2011) [in Russian].

    Google Scholar 

  12. Yu. S. Fedorov, B. Ya. Zil’berman, A. S. Aloi, E. A. Puzikov, A. Yu. Shadrin, and M. Yu. Alyapyshev, “Problems of modernization of spent nuclear fuel extraction processing,” Russ. J. General Chem. 81, 1932–1948 (2011).

    Article  Google Scholar 

  13. M. Carrott, C. Gregson, and R. Taylor, “Neptunium extraction in an advanced PUREX process and the EURO-GANEX process,” Nat. Nucl. Lab. Sci. 3, 14–20 (2015).

    Google Scholar 

  14. C. S. Dileep, J. Poonam, P. S. Dhami, P. V. Achuthan, A. Dakshinamoorthy, B. S. Tomar, S. K. Munshi, and P. K. Dev, Desalination 232, 157–165 (2008).

  15. V. P. Pishchulin and A. A. Rudik, “Construction and calculation of plant for treatment of irradiated nuclear fuel,” in Innovation Technologies of Atomic Engineering and Industry: Coll. Papers dedicated to 55th Anniversary of STI NIYaU MIF (Seversk, STI NIYaU MIFI, 2014), pp. 88–90.

    Google Scholar 

  16. S. N. Kladiev, S. M. Slobodyan, and V. P. Pishchulin, “Automation of preparation of uranium solutions,” Tsvetn. Metall., No. 8, 77–81 (2014).

    Google Scholar 

  17. S. N. Kladiev, I. A. Kolodnikov, I. A. Maksimov, and V. P. Pishchulin, “Improving the preparation of solutions pre-extraction with providing an automated start of centrifuges in apparatus for reprocessing of spent nuclear fuel,” Tsvetn. Metall., No. 1, 66–70 (2012).

    Google Scholar 

  18. V. V. Orlov, V. A. Seliverstov, and V. A. Tishchenko, White Book of Nuclear Engineering, Ed. by E. O. Adamov, (Moscow, GUP NIKIET, 1998) [in Russian].

  19. A. A. Kopyrin, A. I. Karelin, and V. A. Karelin, Technology of Production and Treatment of Nuclear Fuel; A Tutorial for Higher Education Institutes (Atomenergoizdat, Moscow, 2006) [in Russian].

    Google Scholar 

  20. V. F. Volkov, A. K. Peshel, S. M. Slobodyan, and I. S. Tyryshkin, “Registration of a pulsed laser beam by a matrix of charge-coupled devices,” Instrum. Exper. Techn. 24, 1522–1524 (1981).

    Google Scholar 

  21. S. M. Slobodyan, “Investigation of the correlation between direct and specular-reflected waves,” Proc. SPIE–1697, Acquisition, Tracking, and Pointing VI, 1992, pp. 213–218. doi 10.1117/12.138171

    Chapter  Google Scholar 

  22. S. M. Slobodyan, “Optimizing phase-space scanning for a dynamic system monitoring chaotic media,” Measur. Techn. 49, 1–6 (2006). doi 10.1007/s11018-006-0053-4

    Article  Google Scholar 

  23. S. M. Slobodyan, “Estimation for fractal of signal/ noise relations,” Measur. Techn. 51, 5–8 (2008).

    Article  Google Scholar 

  24. M. S. Slobodyan and S. A. Slobodyan, “Method of acoustic sensor diagnosis,” Measur. Techn. 51, 798–801 (2008).

    Article  Google Scholar 

  25. S. M. Slobodyan and V. P. Kuts, “The improved dust and aerosol collection efficiency by N-step system,” Bezopasnost’ Zhiznedeyatel’nosti, No. 8, 55–59 (2014).

    Google Scholar 

  26. S. M. Slobodyan and V. P. Kuts, “Effectiveness of dust and aerosol catching by N-stepped system,” Izv. Altaisk. Gos. Univ. 1, 257–261 (2014).

    Article  Google Scholar 

  27. wwwrosatomru.

Download references

Author information

Authors and Affiliations

Authors

Corresponding author

Correspondence to S. M. Slobodyan.

Additional information

Original Russian Text © I.S. Vislov, V.P. Pischulin, S.N. Kladiev, S.M. Slobodyan, 2016, published in Teploenergetika.

Rights and permissions

Reprints and permissions

About this article

Check for updates. Verify currency and authenticity via CrossMark

Cite this article

Vislov, I.S., Pischulin, V.P., Kladiev, S.N. et al. Current state of nuclear fuel cycles in nuclear engineering and trends in their development according to the environmental safety requirements. Therm. Eng. 63, 581–586 (2016). https://doi.org/10.1134/S0040601516050104

Download citation

  • Published:

  • Issue Date:

  • DOI: https://doi.org/10.1134/S0040601516050104

Keywords

Navigation