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Convective and diffusive interchannel transfer in fuel assemblies of a fast-reactor core

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Abbreviations

d:

the fuel-element diameter

dh :

the hydraulic diameter

e:

the signal from a sensor

G:

the coolant flow rate

h:

the enthalpy, and also the pitch of the spacing wire wrap

m:

the number of cells interacting with the i-th cell

M:

the coordinate of a point

Q:

the heat flux

S:

the lattice pitch

t:

the temperature

W:

the velocity of the coolant

Z:

a coordinate

α:

the initial phase of the wire wrap

β:

the transfer inequivalence coefficient

Δ:

the width of the gap between perimeter fuel elements and the can

ε:

the parameter of equivalent thermal conductivity of the fuel elements

λ:

the pressure loss

μ:

is the interchannel transfer coefficient

π:

the perimeter

ρ:

the density

τ:

the tangential stress

ϕ:

the phase of the wrap

ω:

the surfce area

eff:

effective

m:

mass or molecular

h:

hydrodynamic

t:

thermal or burbulent

p:

peripheral

c:

convective

i, j:

cell numbers

ij:

number of gap between cells

ce:

central

Literature Cited

  1. A. V. Zhukov, A. P. Sorokin, P. A. Ushakov, and Yu. S. Yur'ev, “Channel thermohydraulic design of fuel-element assemblies for nuclear reactors,” At. Énerg.,51, No. 5, 307–311 (1981).

    Google Scholar 

  2. J. Rogers and N. Todreas, Heat Transfer in Rod Bundle, ASME (1968).

  3. A. V. Zhukov et al., Preprint FÉI-413 (1973).

  4. L. Ingesson and S. Hedberg, Heat Transfer,3, FC 7. 11, 1–11 (1970).

    Google Scholar 

  5. A. V. Zhukov et al., Preprint FÉI-665 (1976).

  6. L. Patch et al., Rep. Intern. Meet. Reactor Heat Transfer, Karlsruhe (1979).

  7. A. V. Zhukov et al., Thermohydraulic Design of Fuel Assemblies for Liquid-Metal-Cooled Fast Reactors [in Russian], Énergoatomizdat, Moscow (1985).

    Google Scholar 

  8. A. V. Zhukov, A. P. Sorokin, and N. M. Matyukhin, Interchannel Transfer in the Fuel Assemblies of Fast Reactors [in Russian], Énergoatomizdat, Moscow (1989).

    Google Scholar 

  9. O. D. Kazachkovskii, A. V. Zhukov, A. P. Sorokin, and N. M. Matyukhin, “Temperature fields in deformed fuel assemblies of fast reactors,” At. Énerg.,65, No. 2, 89–97 (1988).

    Google Scholar 

  10. A. V. Zhukov et al., Preprint FÉI-556, Obninsk (1975).

  11. Y. Okamoto et al., Progress in Sodium Cooled Fast Reactor Engineering, Monako, IAEA/SM-130/5 (1970).

  12. J. Skok, Progress in Heat and Mass Transfer,7, 251–262 (1973).

    Google Scholar 

  13. W. Baumann et al., Rep. Intern. Heat Transfer Seminar, Trogir, Yugoslavia (1971).

  14. R. Collingham et al., Nucl. Eng. Design,24, No. 3, 393–400 (1973).

    Google Scholar 

  15. A. V. Zhukov et al., Preprint FÉI-799 (1977).

  16. A. V. Zhukov et al., Preprint FÉI-867 (1978).

  17. L. Bolle et al., Intern. Meet. on Reactor Heat Transfer, Karlsruhe (1973).

  18. M. Fontana et al., Trans ANS,15, No. 2, 855 (1972).

    Google Scholar 

  19. V. M. Gryazev et al., Thermophysics and Hydrodynamics of the Core and Steam Generators of Fast Reactors [in Russian], Prague (1978), p. 182.

  20. C. Chiu et al., Intern. Meet. on Reactor Heat Transfer, Karlsruhe (1979).

  21. A. Hanson et al., COO-2245-51TR (1977).

  22. K. Mijaguchi et al., IWGFR/29 (1979), pp. 58–75.

  23. E. Waters, HW-70178, Rev. Hanford Labor. (1963).

  24. T. Shimazaki et al., Heat Transfer Conf. of 1956, TID-7529, Book 1, U. S. Atomic Energy Commision (1957), p. 273.

  25. E. Khan et al., Nucl. Eng. Des.,35, No. 1, 1–12 (1975).

    Google Scholar 

  26. C. Chiu et al., Trans ANS,30, 547–548 (1978).

    Google Scholar 

  27. B. V. Dzyubenko, Inzh.-fiz. Zh., No. 5, 777–783 (1979).

    Google Scholar 

  28. N. Buleev, in: Proc. 3d Intern. Conf. Peaceful Uses of Atomic Energy, New York (1965).

  29. W. Sha et al., Trans. ANS,24, 344–346 (1976).

    Google Scholar 

  30. J. Lafay et al., CEA-CONF-3491 (1975).

  31. J. Lorenz et al., Nucl. Eng. Des.,420, No. 2, 315 (1977).

    Google Scholar 

  32. Y. Chen et al., Trans. ANS,19, No. 1, 323–324 (1974).

    Google Scholar 

  33. D. Rowe et al., Trans. ANS,10, No. 2, 655 (1967).

    Google Scholar 

  34. L. N. Polyanin, “Heat and mass transfer in rod bundles during longitudinal flowaround by a turbulent liquid flow,” At. Énerg.,26, No. 3, 279–280 (1969).

    Google Scholar 

  35. R. Nijsing et al., Nucl. Eng. Des.,30, No. 2, 145–185 (1974).

    Google Scholar 

  36. R. Roidt et al., Teploperedacha,96, No. 2, 61–68 (1972).

    Google Scholar 

  37. G. Marckoczy et al., Trans ANS,20, No. 1, 758–761 (1975).

    Google Scholar 

  38. B. N. Gabrianovich et al., Thermophysical Research [in Russian], VIMI, Moscow (1977), pp. 23–33.

    Google Scholar 

  39. K. Rudzinski et al., Can. J. Chem. Eng.,50, No. 2, 297 (1972).

    Google Scholar 

  40. W. Seale, Intern. J. Heat and Mass Trans.,24, No. 4, 768–770 (1981).

    Google Scholar 

  41. A. V. Zhukov et al., Preprint FÉI-1816 (1986).

  42. A. V. Zhukov et al., Preprint FÉI-757 (1977).

  43. R. Bowring, AEEW-R582, London (1968).

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Physics and Energy Institute (FÉI), Obninsk. Translated from Atomnaya Énergiya, Vol. 71, No. 2, pp. 114–123, August, 1991.

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Zhukov, A.V., Matyukhin, N.M., Sorokin, A.P. et al. Convective and diffusive interchannel transfer in fuel assemblies of a fast-reactor core. At Energy 71, 627–635 (1991). https://doi.org/10.1007/BF01121653

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