Skip to main content

Advertisement

Log in

Development, analysis, and simulation of a technological structure for reprocessing irradiated nuclear fuel from nuclear power plants by water-extraction methods

  • Published:
Atomic Energy Aims and scope

The development of closed water-extraction technologies for reprocessing irradiated fuel from nuclear power plants as part of a closed nuclear fuel cycle based on the purex process, including units for obtaining and preparing irradiated fuel for reprocessing, separating actinides with their purification and obtaining commercial forms, as well as concentrating and immobilizing process radwastes is analyzed. It is shown that a formalized description can be given for the elements of the technological structure using generalizing terms, making it possible to propose an approach to constructing a hierarchical model of the technological process with number coding of the levels of production–unit–operation–flow, in turn making it possible to construct graphical structural diagrams showing the couplings between units and operations as well as to construct a mathematical model of the materials balance.

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. B.Ya. Zilberman, “Development of the purex process for reprocessing high-burnup fuel from nuclear power plants in a closed NFC from the standpoint of localizing long-lived radionuclides,” Radiokhimiya, 42, No. 1, 3–15 (2000).

    Google Scholar 

  2. V. N. Romanovskii, A. Yu. Shadrin, B. Ya. Zilberman, et al., “Extraction removal of long-lived radionuclides from high-level wastes,” Vopr. Radiats. Bezopasn. (PO Mayak, Ozersk), No. 1, 3–19, No. 2, 5–14 (2004).

  3. Minimization of Radioactive Waste from Nuclear Reprocessing Plants and the Back-End of the Nuclear Fuel Cycle, Edited by A. F. Tsarenko, Tech. Rep. Ser. No. 377, IAEA, Vienna (1992).

  4. M. I. Ojovan and W. Lee, “Immobilization of radioactive wastes in glass,” in: An Introduction to Nuclear Waste Immobilization, Elsevier, London (2005), pp. 213–249.

    Chapter  Google Scholar 

  5. N. A. Shulga and I. D. Sokolova, At. Tekh. Rubezhom, No. 9, 3–19 (2008).

  6. S. Stoler and R. Richards (eds.), Reprocessing Nuclear Fuel [Russian translation], Atomizdat, Moscow (1964), pp. 184–230.

    Google Scholar 

  7. “Symposium on Production Technology of 237Np and 2j8Pu,” Ind.. Eng. Chem., Suppl.: Process Design Develop., 3, No. 4, 296–327 (1964).

  8. V. M. Kolobashkin, P. M. Rubtsov, P. A. Ruzhanskii, and V. D. Sidorenko, Radiation Characteristics of Irradiated Nuclear Fuel, Energoatomizdat, Moscow (1983).

    Google Scholar 

  9. B. Ya. Zilberman, V. M. Mosyazh, and V. A. Starchenko, “The influence of daughter radionuclides on Purex process parameters,” J. Radioanalyt. Nucl. Chem., 143, No. 1, 67–70 (1990).

    Article  Google Scholar 

  10. L. Abrams, “Fuel reprocessing – commercial experience,” Reactor and Fuel Proc. Technol., 12, No. 2, 181–194 (1969).

    Google Scholar 

  11. Y. Hajimu, E. Omori, N. Miura, et al., “Results of 106Pu and 95Zr decontamination studies in the co-decontamination cycle of the Tokai reprocessing plant,” in: Proc. Int. Conf. of Solvent Extr. in the Process Industries (ISEC90), Elsevier, NY (1992), Pt. A, pp. 657–662.

  12. H. Iwabuchi, K. Sasaki, K. Koyama, et al., “Conceptual study for a computer-aided extraction-status diagnostic system for the Pu–U partition cycle of the Tokai reprocessing plant,” ibid., pp. 705–710.

  13. P. Baron, P. Miquel, J. Dormant, et al., “Extraction cycles design for La Hague plants,” in: Proc. Int. Conf. Global’93, USA (1993), pp. 63–69.

  14. H. Masson, H. Houguier, C. Bernar, et al., “Advanced purex process and waste minimization at La Hage,” in: Proc. Int. Conf. on Nuclear Waste Manag. and Environ. Remedial, Czech Rep. (1993), Vol. 1, pp. 351–360.

  15. N. Miura, M. Watahiki, Yo. E. Nakamura, et al., “Operation experience and anti-foam study at the Tokai reprocessing plant,” in: Proc. Int. Conf. Global’97, Japan (1997), Vol. 2, pp. 1238–1243.

  16. F. Drain, J.-P. Moulin, and D. Hugelmann, “Advanced solvent management in reprocessing: five years of industrial experience,” in: Int. Solvent Extraction Conf. ISEC’96, Melbourne, Australia (1996), Vol. 1, pp. 789–793.

  17. E. G. Dzekun, V. M. Dubrovsky, and B. S. Zakharkin, “Commercial reprocessing of WWER-440 spent fuel,” in: Proc. 3rd Int. Conf. on Nucl. Fuel Reproc. & Waste Manag. RECOD’91. Japan, 1991, Vol. 1, pp. 44–48.

  18. Yu. V. Glagolenko, E. G. Dzekun, and S. I. Rovnyi, “Reprocessing of irradiated nuclear fuel at the RT-1 complex: history, problems, prospects,” Vopr. Radiats. Bezopasn. (PO Mayak, Ozersk), No. 2, 3–12 (1997).

  19. S. I. Rovnyi, L. V. Nedelina, V. M. Tarakanov, et al., “On the particulars of separation of plutonium and neptunium for the conditions of reprocessing spent nuclear fuel at the RT-1 complex,” Radikhimiya, 40, No. 4, 331–335 (1998).

    Google Scholar 

  20. E. G. Dzekun, B. Ya. Zilberman,Yu. P. Zhirnov, et al., “Evaporation procedures in spent fuel reprocessing,” in: Proc. of 3rd Int. Conf. on Nucl. Fuel Reproc. & Waste Manag. RECOD’91, Japan (1991), Vol. 1, pp. 433–436.

  21. L. N. Lazarev, R. I. Lyubtsev, V. A. Lebedev, et al., “Construction of the plant RT-2 as a way for solving the problem of WWER-1000 spent fuel management in Russia,” in: Abstr. 3rd Ann. Sci. Conf. of Nucl. Soc. Intern. NT’92, St. Petersburg (1992), pp. 14–16.

  22. B. Ya. Zilberman, M. N. Makarychev-Mikhailov,V. F. Saprykin, et al., “Regeneration of spent extracting agent TBP,” Radiokhimiya, 44, No. 3, 252–259 (2002).

    Google Scholar 

  23. B. Ya. Zilberman, Yu. S. Fedorov, E. N. Mishin, et al., “Superpurex as an optimized TBP-compatible process for long-lived radionuclide partitioning,” in: Proc. Int. Conf. Global’2003, USA (2003), pp. 503–507.

  24. M. V. Gladyshev, B. Ya. Zil’berman, V. V. Revyakin, et al., “Single-cycle scheme fof extractive reprocessing of spent fuel from nuclear power plants with sorption additional purification of uranium reextract,” Vopr. Radiats. Bezopasn. (PO Mayak, Ozersk), No. 4, 27–32 (1998).

  25. V. I. Volk, “New approaches to reprocessing spent nuclear fuel,” in: Abstr. of Reports at the 3rd Russian Conf. on Radiochemistry “Radiokhimiya-2000,” St. Petersburg (2000), pp. 100–101.

  26. S. A. Bartenev, B. Ya. Zil’berman,V. M. Esimantaovskii, et al., Method of Oxidative Destruction of Ammonium Salts, RF Patent No. 2329554, Byull. Izobr. Tovar. Znaki, No. 20 (2008).

  27. P. M. Gavrilov,Yu. A. Revenko, E. G. Kudryavtsev, et al., “Simplified PUREX-promising technology of SNF treatment for the plant of the next generation,” in: Proc. Int. Conf. Advanced Nuclear Fuel Cycles and Systems Global’2007, USA, CD, pp. 1484–1489.

  28. P. M. Gavrilov, E. G. Kudryavtsev, and Yu. A. Revenko, “Experimental demonstration center on MCC as a prototype of the 3rd generation plant for thermal reactor SNF reprocessing,” in: Proc. Int. Conf. Global’2009 on Nuclear Fuel Cycles: Sustainable Options and Industrial Perspectives, USA, CD (2009), pp. 66–69.

Download references

Author information

Authors and Affiliations

Authors

Additional information

Translated from Atomnaya Énergiya, Vol. 107, No. 5, pp. 273–285, November, 2009.

Rights and permissions

Reprints and permissions

About this article

Cite this article

Zilberman, B.Y., Puzikov, E.A., Ryabkov, D.V. et al. Development, analysis, and simulation of a technological structure for reprocessing irradiated nuclear fuel from nuclear power plants by water-extraction methods. At Energy 107, 333–347 (2009). https://doi.org/10.1007/s10512-010-9233-z

Download citation

  • Received:

  • Published:

  • Issue Date:

  • DOI: https://doi.org/10.1007/s10512-010-9233-z

Keywords

Navigation