Skip to main content
SpringerLink
Log in

Method of Calculating Fission Product Mass Transfer in Multizone Reactor Problems

  • Published:
Atomic Energy Aims and scope

An analytic solution is given for a system of first-order inhomogeneous linear differential equations describing the mass transfer of fission products in radioactive decay chains of arbitrary complexity and length by means of a system of an infinite number of working zones separated by radiation safety barriers. The computational procedure is implemented in the TARUSA system of computer codes, making it possible to take into account the individual behavior of different fi ssion products as they pass through radiation safety barriers and the arbitrary dependence of the basic initial data on the operating time of the reactor. The TARUSA codes possess their own libraries of nuclear-physical constants. A comparison is made with the normative example of the calculation of the residual power release from irradiated fuel from the international standard ISO 10645.

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. H. Bateman, “Solution of a system of differential equations occurring in the theory of radio-active transformations,” in: Proc. Cambridge Philos. Soc., 16, 423–427 (1910).

  2. N. G. Gusev, V. P. Mashkovich, and G. V. Obvintsev, Gamma Radiation of Radioactive Isotopes and Fission Products: Theory and Tables, Gosizdat. Fiz.-Mat. Lit., Moscow (1958).

    Google Scholar 

  3. A. P. Veselkin and Yu. A. Egorov (eds.), Engineering Calculation of the Protection of Nuclear Power Plants, Atomizdat, Moscow (1976).

  4. N. G. Gusev and P. P. Dmitriev, Handbook of Radioactive Chains, Atomizdat, Moscow (1978).

    Google Scholar 

  5. O. Hermann and R. Westfall, ORIGEN-S: SCALE System Module to Calculate Fuel Depletion, Actinide Transformation, Fission Product Buildup and Decay, and Associated Radiation Source Terms, NUREG/CR-0200, Rev. 5 (1995).

  6. R. Forest, FISPACT-2003: User Manual, EASY Documentation Ser. UKAEA FUS 485 (2003).

  7. A. P. Veselkin, M. E. Netecha, A. V. Nikitin, et al., Calculation of the Activity of Fission Products: Description of the Code OSKOLKI, NIKIET Report No. E16.293-365 (1973).

  8. M. E. Netecha, A. V. Nikitin, S. F. Mocharnyi, et al., Transfer of Fission Products along the Loop of a Boiling-Water Reactor (TARUSA code), NIKIET Report No. 160-182-2119 (1985).

  9. A. V. Nikitin, M. E. Netecha, and S. F. Mocharnyi, Calculation of the Activity of Fission Products (description of the TARUSA-2 code). NIKIET Report No. Е160-2275 (1987).

  10. A. V. Nikitin, V. P. Vasyukhno, A. A. Gordeev, et al., TARUSA-9: Software Tool for Calculating the Rate of Formation and Mass Transfer of Radionuclides in Nuclear Power Plants in Complex Dynamic Processes: Code Description, NIKIET Report No. 160-117-6049 (2002).

  11. A. V. Nikitin, A. A. Gordeev, M. E. Netecha, et al., Analytical Testing of the TARUSA-9 Code, NIKIET Report No. 160-117-6136 (2002).

  12. A. V. Nikitin, A. A. Gordeev, M. E. Netecha, et al., Verification of the TARUSA-9 Software, NIKIET Report No. 160-117-6136 (2002).

  13. MCNP – a General Monte Carlo N-Particle Transport Code, LA-12625-M, vers. 4B (1997).

  14. A. V. Nikitin, V. P. Vasyukhno, and M. E. Netecha, TARLIB: System of Libraries of Nuclear-Physical Constants for Calculating the Formation and Mass Transfer of Radionuclides in the Loops of Nuclear Power Plants, NIKIET Report No. 160-117-6104 (2002).

  15. V. P. Vasyukhno, A. A. Gordeev, A. V. Nikitin, et al., Development and Modernization of Nuclear Data Libraries for the TARUSA Program, NIKIET Report No. 214-168-10340 (2013).

  16. J.-Ch. Sulet, J. Kopecky, and R. Forrest, The European Activation File, EAF-99 Decay Data Library, UKAEA FUS 409 (1998).

  17. The Japanese Evaluated Nuclear Data Library, Vers. JENDL-3. JAERI-1316 (1990).

  18. The JEFF-3.1.1 Nuclear Data Library, JEFF Rep. 22, Variation Results from JEFF-2.2 to JEFF-3.1.1. OECD/NEA6807 (2009).

  19. ISO 10645, Nuclear Energy-Light Water Reactors – Calculation of the Decay Heat Power in Nuclear Fuels (1992), 1st ed.

Download references

Author information

Authors and Affiliations

  1. Dollezhal Research and Development Institute of Power Engineering (NIKIET), Moscow, Russia

    A. V. Lopatkin, A. V. Nikitin, A. V. Mikhailov, A. A. Gordeev & V. P. Vasyukhno

Authors
  1. A. V. Lopatkin
    View author publications

    You can also search for this author in PubMed Google Scholar

  2. A. V. Nikitin
    View author publications

    You can also search for this author in PubMed Google Scholar

  3. A. V. Mikhailov
    View author publications

    You can also search for this author in PubMed Google Scholar

  4. A. A. Gordeev
    View author publications

    You can also search for this author in PubMed Google Scholar

  5. V. P. Vasyukhno
    View author publications

    You can also search for this author in PubMed Google Scholar

Corresponding author

Correspondence to A. V. Nikitin.

Additional information

Translated from Atomnaya Énergiya, Vol. 128, No. 1, pp. 6–11, January, 2020.

Rights and permissions

Reprints and permissions

About this article

Check for updates. Verify currency and authenticity via CrossMark

Cite this article

Lopatkin, A.V., Nikitin, A.V., Mikhailov, A.V. et al. Method of Calculating Fission Product Mass Transfer in Multizone Reactor Problems. At Energy 128, 5–10 (2020). https://doi.org/10.1007/s10512-020-00642-2

Download citation

  • Received:

  • Published:

  • Issue Date:

  • DOI: https://doi.org/10.1007/s10512-020-00642-2

Search

Navigation