Skip to main content
Log in

Temperature fields in fast reactor fuel assemblies with shape changes

  • Articles
  • Published:
Soviet Atomic Energy Aims and scope

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.

Literature Cited

  1. A. A. Proshkin, Yu. I. Likhachev, A. N. Tubov, et al., “An analysis of experimental data on fast reactor fuel assembly shape changes,” At. Énerg.,50, No. 4, 13–17 (1981).

    Google Scholar 

  2. Yu. Buksha, L. Zabudko, I. Kravchenko, et al., “An analysis of fast reactor fuel assembly performance taking into account their mechanical interaction in the core and refuelling line capabilities,” in: Predictions and Experience of Core Distribution Behavior, No. 1/3, National Nuclear Corporated Limited, Wilmslow, England (1984), p. 22.

    Google Scholar 

  3. J. Marbach, “Comportement d'un faisceau d'aigulles Phénix sous irradiation,” in: Irradiation Behaviour of Metallic Materials for Fast Reactor Components, CEA-DMECH-B. P, No. 2-91190, Gif-sur-Yvette, France) 1979), pp. 269–301.

  4. A. V. Zhukov, N. M. Matyukhin, E. V. Nomofilov, et al., “Temperature fields in nonstandard and deformed fast reactor fuel lattices,” in: Fast Reactor Core and Steam Generator Thermal Physics and Hydrodynamics [in Russian], ONTI ChSKAÉ, Prague (1978), pp. 132–145.

    Google Scholar 

  5. A. V. Zhukov, N. M. Matyukhin, and E. Ya. Sviridenko, Temperature Fields in Fast Reactor Deformed Fuel Lattices with Uniform and Nonuniform Thermal Loads: Preprint FÉI-909 [in Russian], Pt. 1, Obninsk (1979).

  6. H. Hishida, Detailed Design Consideration on Wire-Spaced LMFBR Fuel Subassemblies under the Effect of Uncertainties and Nonnominal Operating Conditions, IWGFR/29, IAEA, Vienna (1979), pp. 29–58.

    Google Scholar 

  7. K. Miki, “Deformation analysis of fuel pins within the wire-wrap assembly of an LMFBR,” Nucl. Eng. Design,52, No. 3, 371–382 (1979).

    Google Scholar 

  8. A. V. Zhukov, N. M. Matyukhin, and E. Ya. Sviridenko, The Influence of Lattice Deformation on Temperature Fields and Thermal Output of Fuel Elements in Characteristic Zones of a Fast Reactor Fuel Assembly Model: Preprint FÉI-979 [in Russian], Obninsk (1980).

  9. R. Möller and H. Tchöke, “Steady-state local temperature fields with turbulent liquid sodium flow in nominal and disturbed bundle geometries with spacer grid,” Nucl. Eng. Design,62, No. 1-3, 69–90 (1980).

    Google Scholar 

  10. B. Vegter, R. Roidt, M. Pechersky, et al., “Effect of rod bowing on the subchannel flow rate in a model reactor rod bundle,” Trans. ANS,35, 585–587 (1980).

    Google Scholar 

  11. V. Schultz, “Experimental investigation of temperature fields in a fast reactor assembly with damaged bundle geometry,” in: Hydrodynamics and Heat Transfer in Sodium-Cooled Fast Reactor Cores and Steam Generators [in Russian], Vol. 1, ONTI ChSKAÉ, Prague (1984), pp. 159–173.

    Google Scholar 

  12. P. Milbauer, “Applying the finite element method to calculate turbulent flow in straight noncircular tubes,” in: Hydrodynamics and Heat Transfer in Sodium-Cooled Fast Reactor Cores and Steam Generators [in Russian], Vol. 1, ONTI ChSKAÉ, Prague (1984), pp. 104–115.

    Google Scholar 

  13. A. V. Zhukov, A. P. Sorokin, and N. M. Matyukhin, “Heat removal in fast reactor cores,” At. Énerg.,58, No. 5, 226–232 (1985).

    Google Scholar 

  14. A. V. Zhukov, P. L. Kirillov, N. M. Matyukhin, et al., Thermal Hydraulic Calculations for Fast Reactor Fuel Assemblies with Liquid Metal Cooling [in Russian], Énergoatomizdat, Moscow (1985).

    Google Scholar 

  15. G. Cognet, “Evaluation en function de l'irradiation du profil de temperature en sortie due faisceau d'assemblage dans le reacteur RAPSODIE,” in: Theses of Papers from the Franco-Soviet Seminar “Questions of Fast Reactor Core Thermal Hydraulics,” 23–25 October, 1986 [in Russian], Cadarach, France.

  16. P. Betten, “Bowing of element and changes in radial coolant temperature profile over subassembly life time,” Trans. ANS,53, 532–533 (1986).

    Google Scholar 

  17. A. V. Zhukov, A. P. Sorokin, P. A. Ushakov, et al., A Thermal Physics Survey of Temperature Regimes in Fast Reactor Assemblies Taking into Account Superheating Factors (Temperature Fields, Superheating Factors): Preprint FÉI-1778 [in Russian], Obninsk (1986).

  18. A. V. Zhukov, A. P. Sorokin, P. A. Ushakov, et al., “An analysis of hot spots in fuel assemblies in fast reactor cores,” At. Énerg.,62, No. 3, 153–158 (1987).

    Google Scholar 

  19. A. V. Zhukov, A. P. Sorokin, P. A. Ushakov, et al., “In-channel thermal hydraulic calculations for nuclear reactor fuel assemblies,”ibid.,51, No. 5, 307–311 (1981).

    Google Scholar 

  20. O. D. Kazachkovskii, A. P. Sorokin, A. V. Zhukov, et al., The Lumped Parameters Method in the Problem of the Temperature Field in Fast Reactor Fuel Assemblies with Shape Changes for Nonadiabatic Boundary Conditions: Preprint FÉI-1672 [in Russian], Obninsk (1985).

  21. O. D. Kazachkovskii, A. P. Sorokin, A. V. Zhukov, et al., Stochastic Nonuniformities of Temperature Fields in Fast Reactor Fuel Assemblies with Shape Changes: Preprint FÉI-1678 [in Russian], Obninsk (1986).

  22. A. V. Zhukov, A. P. Sorokin, P. A. Ushakov, et al., A Thermal Physics Survey of Temperature Regimes in Fast Reactor Assemblies Taking into Account Superheating Factors. Methods and Programs for Thermal Hydraulic Calculations for Fast Reactor Assemblies: Preprint FÉI-1817 [in Russian], Obninsk (1986).

Download references

Authors

Additional information

Translated from Atomnaya Énergiya, Vol. 65, No. 2, pp. 89–97, August, 1988.

Rights and permissions

Reprints and permissions

About this article

Cite this article

Kazachkovskii, O.D., Zhukov, A.V., Sorokin, A.P. et al. Temperature fields in fast reactor fuel assemblies with shape changes. At Energy 65, 627–636 (1988). https://doi.org/10.1007/BF01270803

Download citation

  • Received:

  • Issue Date:

  • DOI: https://doi.org/10.1007/BF01270803

Keywords

Navigation