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Investigations of transitional and accident operating conditions in models of fast-reactor fuel-element bundles

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Literature Cited

  1. A. Walters and A. Reynolds, Fast-Neutron Breeder Reactors [Russian translation], Énergoatomizdat, Moscow (1986).

    Google Scholar 

  2. A. V. Zhukov, A. P. Sorokin, and N. M. Matyukhin, Transfer between Channels in Fast-Reactor Fuel Element Bundles: Computer Programs and Practical Application [in Russian], Énergoatomizdat, Moscow (1991).

    Google Scholar 

  3. A. V. Zhukov, A. P. Sorokin, and N. M. Matyukhin, Transfer between Channels in Fast-Reactor Fuel Element Bundles [in Russian], Énergoatomizdat, Moscow (1989).

    Google Scholar 

  4. A. P. Sorokin, A. V. Zhukov, Yu. N. Korienko, and P. A. Ushakov, "Macrotransfer equations in reactor fuel-element bundles (multiphase flow)," Preprint FÉI-1800, Power Physics Institute (FÉI), Obninsk (1986).

  5. D. Rowe, "COBRA IIIC: thermal-hydraulic analysis of rod bundle nuclear fuel elements," BNWL-1695 (1973).

  6. W. Sha, R. Schmitt, and R. Huebotter, "Boundary-value thermal hydraulic analysis of a reactor fuel rod bundle," Nucl. Sci. Eng.,59, No. 2, 140–160 (1976).

    Google Scholar 

  7. M. Arai and H. Hirata, "Numerical calculation for two-phase flow analysis in pin bundles," Nucl. Eng. Des.,82, Nos. 2–3, 157–169 (1984).

    Google Scholar 

  8. M. Bottom and G. Willerding, "Advanced solution algorithms for transient multidimensional thermohydraulic flow problems in complex geometries with the COMMIX-2/KFK program," Nucl. Eng. Des.,100, Nos. 3, 351–366 (1987).

    Google Scholar 

  9. H. Ninokata, "Analysis of low-heat-flux sodium boiling tests in a 37-pin bundle by the two-fluid model computer code SABENA," Nucl. Eng. Des.,97, No. 12, 233–246 (1987).

    Google Scholar 

  10. Yu. N. Kuznetsov, Heat Transfer in the Problem of Nuclear Reactor Safety [in Russian], Énergoatomizdat, Moscow (1989).

    Google Scholar 

  11. G. P. Bogoslovskaya, I. L. Bogatyrev, A. V. Zhukov, and A. P. Sorokin, "Two-fluid model for calculating two-phase flow in heat-producing reactor assemblies," Preprint FÉI-2166 (1991).

  12. G. P. Bogoslovskaya, I. L. Bogatyrev, A. V. Zhukov, and A. P. Sorokin, Reaction between phases in two-phase gas-liquid flows in channels, Preprint FÉI-2149 (1990).

  13. Yu. N. Korienko, V. S. Kuzevanov, and A. P. Sorokin, "The technique of calculation of nonequilibrium two-phase flows in pin bundles using quasi-two-dimensional approaches and subchannel approximation," FED (Vol. 99) and HTD (Vol. 155), American Nuclear Society, New York (1990), pp. 321–330.

    Google Scholar 

  14. Y. Kikuch, "Sodium boiling experiments: loss-of-flow conditions," Nucl. Eng. Des.,66, No. 3, 356–366 (1981).

    Google Scholar 

  15. N. A. Kolev, "A three-fluid diffusion model of the three-phase, three-dimensional computer code IVA 2/001," Nucl. Tech.,78, No. 1, 95–131 (1987).

    Google Scholar 

  16. J. Seiler, G. Cognet, E. Leborgne, et al., "French LMFBR core thermal-hydraulic studies for nominal and accident conditions," Nucl. Eng. Des.,124, No. 3, 403–415 (1990).

    Google Scholar 

  17. F. Huber and W. Peppler, "Boiling and dry-out behind local blockages in sodium-cooled rod bundles," Nucl. Eng. Des.,82, No. 3, 341–363 (1984).

    Google Scholar 

  18. O. Dwyer, "Incipient boiling superheat for sodium in turbulent channel flow effects on heat flux and flow rate," J. Heat Mass Transfer,16, No. 5, 971–984 (1973).

    Google Scholar 

  19. F. Huber, K. Schleisiek, D. Wall, et al., "Comparison study of thermohydraulic computer code simulations of sodium boiling under loss of flow conditions," Proc. 13th Meeting of the Liquid Metal Boiling Working Group Winfrith, Dorchester, Dorset, UK, 27–29 September 1988.

  20. E. F. Ivanov and O. Yu. Abramychev, "Experimental investigations of sudden boiling processes of a liquid-metal coolant in an circular channel," Preprint FÉI-2197 (1991).

  21. K. Haga, K. Yamaguchi, and F. Namekawa, "Experimental study on the effect of fission product gas release into a blockage wake region using a simulated LMFBR fuel subassessment," Nucl. Eng. Des.,83, No. 3, 329–340 (1984).

    Google Scholar 

  22. P. Bergeonnean and B. Ramean, "Conditions for locally astable boiling in a pin bundle," Proc. International Conference of Science and Technology on Fast Reactor Safety, Guernsey, 12–16 May 1986, Vol. 2, pp. 445–450.

  23. F. Mantlik, A. V. Zhukov, A. P. Sorokin, et al., "Summary of thermal investigations of fuel element assemblies with partial blockage of the flow cross sections," Report UJV6057-T Prague, Joint Scientific and Technical Publishing House, Institute of Nuclear Research (Rzhezh) (1982).

  24. M. Votani and K. Haga, "Experimental investigation of sodium boiling in partially blocked fuel subassemblies," Nucl. Eng. Des.,82, No. 3, 319–328 (1984).

    Google Scholar 

  25. K. Haga and K. Yamaguchi, "Boiling behind local blockages in an LMFBR," J. Nucl. Sci. Techn.,28, No. 8, 619–636 (1985).

    Google Scholar 

  26. J. Macdongall and J. Lillington, "The SABRE code for fuel rod cluster thermohydraulics," Nucl. Eng. Des.,82, Nos. 2–3, 171–190 (1984).

    Google Scholar 

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Authors
  1. A. V. Zhukov
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  2. A. P. Sorokin
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  3. P. A. Ushakov
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  4. G. P. Bogoslovskaya
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  5. I. L. Bogatyrev
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Additional information

Power Physics Institute (FÉI), Obninsk. Translated from Atomnaya Énergiya, Vol. 73, No. 4, pp. 339–345, November, 1992.

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Zhukov, A.V., Sorokin, A.P., Ushakov, P.A. et al. Investigations of transitional and accident operating conditions in models of fast-reactor fuel-element bundles. At Energy 73, 850–856 (1992). https://doi.org/10.1007/BF00739626

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  • DOI: https://doi.org/10.1007/BF00739626

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