Skip to main content
SpringerLink
Log in

Comparative analysis of empirical correlations for calculating heat-flux crisis in VVER rod bundles

  • Articles
  • Published:
Atomic Energy Aims and scope

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

References

  1. M. Lee and L. Liao, "An assessment of the critical heat flux approaches of thermal-hydraulic system analysis codes using bundle data from the heat transfer research facility," Nucl. Technol.,105, 216–230 (1994).

    Google Scholar 

  2. D. Groeneveld, S. Cheng, and T. Doan, "1986 AECL-UO critical heat flux lookup table," Heat Transfer Eng., 7, No. 1–2 (1986).

  3. G. Lellouche, "The boiling transition. Analysis and data comparisons," Nucl. Eng. Design,116, No. 2 (1989).

  4. V. N. Smolin, S. V. Shpanskii, and V. K. Polyakov, "Method for calculating the heat-transfer crisis in smooth rod bundles," Scientific-Research and Design Institute of Electrotechnical Apparatus Report No. 26.758 (1977).

  5. L. L. Kobzar', A. I. Suslov, and D. Yu. Makhov, "Cellular bank of experimental data on heat-flux crisis accompanying boiling of water in rod bundles," Report of the Institute of Nuclear Reactors of the Russian Science Center "Kurchatov Institute," No. 32/1-374-89 (1989).

  6. L. L. Kobzar' and A. I. Suslov, "Verification of the computational model for critical heat fluxes in the program RELAP5/MOD3 on the basis of databanks," Report of the Institute of Nuclear Reactors of the Russian Science Center "Kurchatov Institute," No. 32/1-1868-92 (1992).

  7. V. N. Smolin, S. V. Shpanskii, and V. K. Polyakov, "Method for calculating heat flux crisis during boiling of the coolant in rod assemblies" in: TF-78 Seminar, Budapest (1978).

  8. Yu. A. Bezrukov, V. I. Astakhov, V. G. Brantov et al., "Experimental investigations and statistical analysis of data on heat-flux crisis in rod bundles for VVER reactor," Teploénergetika, No. 2, 80–82 (1976).

  9. L. L. Kobzar', A. I. Suslov, and D. Yu. Makhov, "Second version of the experimental-databank of the Institute of Atomic Energy on Heat Flux-Crisis," Report of the Institute of Nuclear Reactors of the Russian Science Center "Kurchatov Institute," No. 32/1-3, parts 1 and 2 (1988).

Download references

Authors
  1. Yu. M. Zhukov
    View author publications

    You can also search for this author in PubMed Google Scholar

  2. G. E. Romantsov
    View author publications

    You can also search for this author in PubMed Google Scholar

Additional information

Institute of Nuclear Reactors, Russian Science Center "Kurchatov Institute". Translated from Atomnaya Énergiya, Vol. 80, No. 1, pp. 15–20, January, 1996.

Rights and permissions

Reprints and permissions

About this article

Cite this article

Zhukov, Y.M., Romantsov, G.E. Comparative analysis of empirical correlations for calculating heat-flux crisis in VVER rod bundles. At Energy 80, 15–19 (1996). https://doi.org/10.1007/BF02415749

Download citation

  • Received:

  • Issue Date:

  • DOI: https://doi.org/10.1007/BF02415749

Keywords

Search

Navigation