Skip to main content
SpringerLink
Log in

Methodological Foundations and Development of Computational Optimization Complexes for Designing Fast Reactors

  • Articles
  • Published:
Atomic Energy Aims and scope

A formulation of the optimal design problem for fast reactors is given and the main difficulties in solving it are examined. The computational software complexes developed at different times and making it possible to find the best reactor characteristics without resorting to variant calculations are reviewed. The particularities of problems, methods of solution and methods of organizing the computational process so as to reduce the computing time are discussed. Ways to improve and develop computational optimization complexes are proposed taking account of current requirements for new-generation fast power reactors and the increased possibilities of computational technology.

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

Access this article

Log in via an institution

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

Instant access to the full article PDF.

Institutional subscriptions

Similar content being viewed by others

References

  1. V. V. Khromov, A. M. Kuzmin, A. A. Kashutin, and Yu. V. Silaev, “Computational optimization complex for fast atomic reactors (ROKBAR),” in: Physics of Nuclear Reactors, Atomizdat, Moscow (1970), Iss. 2, pp. 3–16.

  2. A. G. Sukharev, A. V. Timokhov, and V. V. Fedorov, Course in Optimization Methods, Fizmatlit, Moscow (2005).

    Google Scholar 

  3. N. I. Geraskin, A. M. Kuzmin, and D. V. Morin, “Algorithms and program for optimizing the composition of the zones of fast reactors,” Vopr. At. Nauki Tekhn. Ser. Fiz. Tekhn. Yad. Reakt., No. 4(33), 50–53 (1983).

  4. N. N. Egorkina, A. M. Kuzmin, S. A. Moskalev, et al., “DOKAR software complex for optimization of fast reactors in interactive mode,” in: Mathematical Models of Nuclear-Power Facilities, Energoatomizdat, Moscow (1993), pp. 5–15.

    Google Scholar 

  5. A. M. Kuzmin, D. V. Morin, and A. E. Novikov, “Two-level optimization system for studying fast reactors,” Vopr. At. Nauki Tekhn. Ser. Fiz. Tekhn. Yad. Reakt., No. 3, 25–30 (1994).

  6. K. Inoue, “Fast reactor design optimization system with a method of nonlinear programming,” Nucl. Sci. Eng., 51, No. 1, 1–9 (1973).

    Google Scholar 

  7. B. A. Afrin and G. B. Usynin, “COB-FL computational complex for determining the optimal depth of fuel burnup,” Vopr. At. Nauki Tekhn. Ser. Fiz. Tekhn. Yad. Reakt., No. 4(33), 36–41 (1983).

  8. V. V. Khromov and V. B. Glebov, “Variational-synthetic methods and their application in neutron-physical studies of reactors,” At. Énerg., 58, No. 5, 360–369 (1985).

    Google Scholar 

  9. R. P. Fedorenko, Approximate Solution of Optimal Control Problems, Nauka, Moscow (1978).

    MATH  Google Scholar 

  10. A. M. Kuzmin, “Methods of solving adjoint equations in nonlinear conditional-critical problems,” At. Énerg., 93, No. 1, 18–27 (2002).

    Google Scholar 

  11. N. I. Geraskin, A. M. Kuzmin, and V. V. Khromov, “Effect of deviations of the initial data on nuclear reactor optimization results,” At. Énerg., 63, No. 1, 3–6 (1987).

    Google Scholar 

  12. A. M. Kuzmin and V. S. Okunev, “Some trends in the changes in the physical characteristics of fast reactors in optimization with constraints on safety functionals,” At. Énerg., 80, No. 6, 429–437 (1996).

    Google Scholar 

  13. A. I. Zinin, V. E. Kolesov, and A. I. Voropaev, “RBR-80 package of applied programs,” Vopr. At. Nauki Tekhn. Ser. Fiz. Tekhn. Yad. Reakt., No. 5, 73–77 (1985).

  14. V. V. Khromov, A. M. Kuzmin, and V. V. Orlov, Method of Successive Linearization in Fast Reactor Optimization Problems, Atomizdat, Moscow (1978).

    Google Scholar 

  15. G. B. Usynin, A. S. Karabasov, and V. A. Chirkov, Fast Reactor Optimization Models, Atomizdat, Moscow (1981).

    Google Scholar 

  16. A. M. Veselov, V. G. Zimin, A. S. Korsun, et al., “SKETCH–THEHYCO software complex for modeling reactor cores with liquid-metal coolant,” Vopr. At. Nauki Tekhn. Ser. Fiz. Tekhn. Yad. Reakt., No. 3, 41–50 (2005).

  17. A. M. Kuzmin and M. F. Khromova, “Linear model of neutron kinetics for studying transient processes in nuclear power plants,” Yad. Fiz. Inzhinir., 4, No. 7, 642–647 (2013).

    Google Scholar 

  18. A. M. Kuzmin and V. I. Moroko, “Optimization of the physical characteristics and uniform partial refueling regimes of a fast reactor,” Vopr. At. Nauki Tekhn. Ser. Fiz. Tekhn. Yad. Reakt., No. 2, 44–50 (2012).

Download references

Author information

Authors and Affiliations

  1. National Nuclear Research University – Moscow Engineering-Physics Institute (NIYaU MIFI), Moscow, Russia

    A. M. Kuzmin

  2. Nauka i Innovatsii Company, Moscow, Russia

    V. V. Orlov

Authors
  1. A. M. Kuzmin
    View author publications

    You can also search for this author in PubMed Google Scholar

  2. V. V. Orlov
    View author publications

    You can also search for this author in PubMed Google Scholar

Additional information

Translated from Atomnaya Énergiya, Vol. 117, No. 1, pp. 3–9, July, 2014.

Rights and permissions

Reprints and permissions

About this article

Check for updates. Verify currency and authenticity via CrossMark

Cite this article

Kuzmin, A.M., Orlov, V.V. Methodological Foundations and Development of Computational Optimization Complexes for Designing Fast Reactors. At Energy 117, 1–7 (2014). https://doi.org/10.1007/s10512-014-9879-z

Download citation

  • Received:

  • Published:

  • Issue Date:

  • DOI: https://doi.org/10.1007/s10512-014-9879-z

Keywords

Search

Navigation