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Basic Questions Concerning the Thermophysics of Nuclear Power

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Abstract

The term “thermophysics” encompasses three areas – hydrodynamics, heat transfer, and technology of coolants. These areas are closely interrelated and influence reactor physics, corrosion processes, and the reliability and safety of a nuclear power system. At the present level of knowledge, when developing prospective fourth-generation reactors and other power systems, the thermophysical processes occurring in the loops must be considered not separately but together, taking account of their mutual influence on the operation of the loops in the nuclear power system. These processes also must be taken into account in order to develop systems for controlling them.

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REFERENCES

  1. Hydrodynamics and Heat Transfer in Nuclear Power Systems, Atomizdat, Moscow (1975).

  2. I. E. Idel'chik, Handbook of Hydraulic Resistance, Mashinostroenie, Moscow (1975).

    Google Scholar 

  3. I. E. Idel'chik, Aerodynamics of Technological Apparatus, Mashinostroenie, Moscow (1983).

    Google Scholar 

  4. S. Kliem, U. Rohde, and F. Weiss, “Analysis of PWR core behavior after entrance underborated water,” Annual Meeting on Nuclear Technology, Rössendorf, Berlin (2003).

    Google Scholar 

  5. D. A. Labuntsov and V. V. Yagov, Mechanics of Two-Phase Systems, MéI, Moscow (2000).

    Google Scholar 

  6. Yu. V. Yudov, S. N. Volkova, and Yu. A. Migrov, “Closure relations for thermohydraulic model of the KORSAR computer code,” Teploénergetika, No. 11, 22–29 (2002).

    Google Scholar 

  7. A. P. Sorokin, E. F. Ivanov, V. L. Mal'kov, et al., “Experimental investigations of heat transfer and stability of the boiling of liquid metal in a natural circulation loop,” Preprint FéI-2631 (1997).

  8. Thermohydraulic Relationships for Advanced Water Cooled Reactors,IAEA-TECDOC-1203, April 2001, Vienna.

  9. P. L. Kirillov, “Experience in operating reactors indicates the need for new thermohydraulic studies,” At. Tekh. Rubezh., No. 9, 3–9 (2003).

    Google Scholar 

  10. P. L. Kirillov, “Transition to supercritical parameters-a way to improve nuclear power plants with water-cooled reactors,” Teploénergetika, No. 12, 6–10 (2001).

    Google Scholar 

  11. V. M. Voronov and T. I. Petrova, “Problems of organizing the water-chemistry at heat-and-power plants,” Teploénergetika, No. 7, 2–6 (2002).

    Google Scholar 

  12. V. M. Voronov, P. N. Nazarenko, and V. K. Pauli, “Some principles for adopting chemical-technological monitoring systems,” Teploénergetika, No. 6, 2-7 (1997).

  13. V. I. Subbotin, M. N. Ivanovskii, and M. N. Arnol'd, Physical and Chemical Principles for Using Liquid-Metal Coolants, Atomizdat, Moscow (1970).

    Google Scholar 

  14. P. N. Martynov, R. Sh. Askhadullin, A. I. Simakov, et al., “Regulation of the oxygen potential of lead coolant,” in: Heat and Mass Transfer and the Properties of Liquid Metals, Obninsk (2002), Vol. 1, pp. 185–187.

    Google Scholar 

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Gulevich, A.V., Efanov, A.D., Kirillov, P.L. et al. Basic Questions Concerning the Thermophysics of Nuclear Power. Atomic Energy 96, 352–357 (2004). https://doi.org/10.1023/B:ATEN.0000038102.35927.ea

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  • DOI: https://doi.org/10.1023/B:ATEN.0000038102.35927.ea

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