Skip to main content
Log in

Liquid-Metal Coolants for Nuclear Power

  • Published:
Atomic Energy Aims and scope

Abstract

Liquid-metal coolants for nuclear power systems are compared taking account of the general laws and individual physical-chemical properties of liquid metals, for which unique nuclear-physical and thermophysical properties, and low vapor pressure at high temperature are characteristic and the experimental data on the properties of metal melts can be generalized on the basis of thermodynamic similarity theory and the thermophysical parameters of these systems can be determined more accurately.

Coolants are ranked under different thermohydraulic conditions: for the same transported power and the same Peclet number, which also fixes the Nusselt and Stanton numbers, for all melts.

It is found that for heavy coolants the reactor core should be “open” with flow sections 10 times greater than for alkali metals. The lead velocity should be less than the sodium velocity by the same amount. For lithium, a core which is twice as compact is admissable, and the lithium velocity should be one-third that of sodium.

The understanding of the microstructure and atomic dynamics of metal melts, physical-chemical processes occuring in such melts, and experience in handling such melts make it possible to adjust their characteristics so as to achieve prescribed performance indicators by using specific additives.

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. V. I. Subbotin, Thoughts on Nuclear Power, OÉÉP RAN, St. Petersburg (1995).

    Google Scholar 

  2. A. D. Efanov and F. A. Kozlov (eds.), Liquid Metals from the First Thermophysical Stand to Large-Scale Nuclear Power, GNTS RF- FÉI, Obninsk (2001).

    Google Scholar 

  3. F. A. Kozlov, L. G. Volchkov, É. K. Kuznetsov, and V. V. Matyukhin, Liquid Metal Coolants for Nuclear Power Systems. Removal and Monitoring of Impurities, Énergoatomizdat, Moscow (1983).

    Google Scholar 

  4. V. I. Subbotin, M. N. Arnol'dov, M. N. Ivanovskii, et al., Lithium, IzdAT, Moscow (1999).

    Google Scholar 

  5. M. N. Arnol'dov, M. N. Ivanovskii, N. I. Loginov, et al., “Development of lithium and sodium- potassium alloy technologies for nuclear power systems for use in space,” in: Physics and Power-Engineering Institute - 50 Years, TSNIIatominform, Moscow (1996), p. 254.

    Google Scholar 

  6. V. I. Subbotin, M. N. Ivanovskii, and M. N. Arnol'dov, Physical-Chemical Principles of the Application of Liquid-Metal Coolants, Atomizdat, Moscow (1970).

    Google Scholar 

  7. B. L. Nevzorov (ed.), Corrosion of Structural Materials, Atomizdat, Moscow (1977).

    Google Scholar 

  8. V. A. Ivanov and O. V. Starkov, “Dissolution of stainless steels in a lithium flow,” At. Tekh. Rubezh., No. 10, 9–13 (1979).

  9. A. L. Shimkevich, “Principles of fluctuation theory of nonuniform melts,” Author's Abstract of Dissertation for Doctor of Physico-Mathematical Sciences, OIVTAN, Moscow (1997).

  10. H. Borgstedt and C. Mathews, Applied Chemistry of Alkali Metals, Plenum Press, New York (1987).

    Google Scholar 

Download references

Author information

Authors and Affiliations

Authors

Rights and permissions

Reprints and permissions

About this article

Cite this article

Subbotin, V.I., Arnol'dov, M.N., Kozlov, F.A. et al. Liquid-Metal Coolants for Nuclear Power. Atomic Energy 92, 29–40 (2002). https://doi.org/10.1023/A:1015050512710

Download citation

  • Issue Date:

  • DOI: https://doi.org/10.1023/A:1015050512710

Keywords

Navigation