Skip to main content
SpringerLink
Log in

A study of the dose-rate field in an irradiator with γ-ray source consisting of spent reactor fuel elements

  • Published:
Soviet Atomic Energy Aims and scope

Abstract

Experiments were performed to determine the distribution of activity along a fuel element from the RFT reactor. It was shown that the dRtrtbutton of activity is satisfactorily described by a cosine function, and that the formulas used to compute the dose rate field of an irradtator with uniformly distributed activity along the radiation source are inapplicable to radiators consisting of fuel elements (the disagreement was 23% for the RFT and 32% for the First Atomic Power Station). Better agreement was obtained between experimental data and values computed by our formulas.

An experimental and theoretical study was made of the dose rate field from a single fuel element and from a hollow, cylindrical irradiator made up of eighteen RFT fuel elements. Working formulas were obtained for computing the dose rate field from spent fuel elements. In computing the dose rate field inside a hollow, cylindrical irradiator made of fuel elements of finite diameter, it was shown that the activity can be considered to be distributed according to a cosine law over the surface of an infinitely thin cylinder with a radius equal to the arithmetic mean of the minimum and maximum radii of the irradiator.

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

Literature Cited

  1. V. I. Sinitsyn, Radiation Equipment and its Use, A Review of Foreign Technology [in Russian], Moscow TsITEI (1961).

    Google Scholar 

  2. V. L. Karpov et al., Atomnaya Énergiya,8, No. 5, 446 (1960).

    Google Scholar 

  3. A. P. Smirnov-Averin, et al., Atomnaya Énergiya,8, No. 5, 446 (1960).

    Google Scholar 

  4. V. V. Gonsharov, et al., in Transactions of the Second International Conference on the Peaceful Use of Atomic Energy [in Russian], Dokl. sovetskikh uchenykh, Vol. 2, Moscow, Atomizdat (1959), p. 243.

    Google Scholar 

  5. Nuclear Reactors, USAEC Reports [in Russian], Vol. 1, Moscow, Izd-vo inostr. lit. (1956).

  6. G. I. Marchuk, Ed., Reactor Critical Masses [in Russian], Moscow, Gosatomozdat (1961).

    Google Scholar 

  7. N. Kaplan and J. Chernick, in Proceedings of the International Conference on the Peaceful Use of Atomic Energy (Geneva, 1955).

  8. B. Price, et al., Radiation Shielding [Translated from the English], Moscow, Izd-vo inostr. lit. (1959).

    Google Scholar 

  9. A. Kh. Breger et al., Problemy fizicheskoi khimii, No. 2, Mowcow Goskhimizdat (1959), p. 132.

    Google Scholar 

  10. N. G. Gusev et al., Shielding Against Radiation from Extended Sources [in Russian], Moscow, Atomizdat (1961).

    Google Scholar 

Download references

Authors
  1. V. E. Drozdov
    View author publications

    You can also search for this author in PubMed Google Scholar

  2. I. M. Zakharova
    View author publications

    You can also search for this author in PubMed Google Scholar

  3. S. P. Dobrovol'skii
    View author publications

    You can also search for this author in PubMed Google Scholar

Additional information

Translated from Atomnaya Énergiya, Vol. 19, No. 4, pp. 367–371, October, 1965

Rights and permissions

Reprints and permissions

About this article

Cite this article

Drozdov, V.E., Zakharova, I.M. & Dobrovol'skii, S.P. A study of the dose-rate field in an irradiator with γ-ray source consisting of spent reactor fuel elements. At Energy 19, 1301–1306 (1965). https://doi.org/10.1007/BF01163836

Download citation

  • Received:

  • Revised:

  • Issue Date:

  • DOI: https://doi.org/10.1007/BF01163836

Keywords

Search

Navigation