Metal Science and Heat Treatment

, Volume 45, Issue 7–8, pp 287–292 | Cite as

Zirconium-Niobium Alloys for Core Elements of Pressurized Water Reactors

  • A. V. Nikulina
Article

Abstract

The main characteristics of niobium-bearing zirconium alloys used for fabricating fuel element claddings of pressurized water reactors are considered. It is shown that the high corrosion and radiation resistance of zirconium parts is provided by the chemical composition, structure, and phase composition of the alloys. The Zr – Nb alloys developed in Russia provide reliable operation of fuel elements and fuel rod arrays in active reactors and serve as a basis for new modifications.

Preview

Unable to display preview. Download preview PDF.

Unable to display preview. Download preview PDF.

REFERENCES

  1. 1.
    V. F. Konovalov, V. L. Molchanov, M. I. Solonin, et al., “Nuclear fuel for power reactors. State of the Art and Perspectives,” in: Nuclear Fuel Cycle, Coll. Rep. [in Russian], Minatom RF, Moscow (2000), pp. 89–100.Google Scholar
  2. 2.
    Yu. K. Bibilashvili, “Development of works aimed at advancing the materials for fuel elements of VVÉR and RBMK reactors,” in: Mater. Seminar in Elektrostal, June 8 – 10, 2000 [in Russian] (2000), pp. 520–537.Google Scholar
  3. 3.
    V. I. Solonin, Yu. K. Bibilashvili, A. V. Nikulina, et al., “Zirconium alloy for fuel assemblies of new generation VVÉR,” in: Int. Topic. Meeting “TopFuel'99,” Avignon, France, 13 – 15 Sept., 1999 (1999), pp. 165–177.Google Scholar
  4. 4.
    M. I. Solonin, Yu. K. Bibilashvili, et al., “VVÉR fuel performance and material development for extended burnup in Russia,” in: Second Int. Symp. VVÉR Reactor Fuel Performance, Bulgaria, 1997 (1997), p. 48.Google Scholar
  5. 5.
    A. V. Nikulina, “State of the art and prospects of zirconium materials evolution for fuel rod claddings and other components of VVÉR type reactors in Russia,” in: Topic. Conf. on Materials and Nuclear Power, UK, 1996 (1996), pp. 157–169.Google Scholar
  6. 6.
    P. V. Shebaldov, M. M. Peregud, A. V. Nikulina et al., “É110 alloy cladding tube properties and condition and impurity content,” in: 12th Int. Symp. on Zr in the Nuclear Industry, ASTM STP 1354, p. 545.Google Scholar
  7. 7.
    A. V. Nikulina, V. A. Markelov, M. M. Peregud, et al., “Zirconium alloy É635 as a material for fuel rod cladding and other components of VVÉR and RBMK cores,” in: 11th Int. Symp. on Zr in the Nuclear Industry, ASTM STP 1295, pp. 785–804.Google Scholar
  8. 8.
    V. F. Kon'kov, A. V. Nikulina, M. M. Peregud et al, “Factors affecting the extra-and intra-reactor corrosion of zirconium claddings of fuel elements,” in: Int.Workshop onWater Chemistry and Intra-Reactor Corrosion (Czechia, 1999), IAEATECDOC-1128 (1999), pp. 103–113.Google Scholar
  9. 9.
    D. Franklin and Che-Ju Li, “Effect of heat flux and irradiation induced in water chemistry on Zircaloy nodular oxidation,” in: Int. Symp. on Zr in the Nuclear Industry, ASTM STP 939 (Philadelphia, 1987) (1987), pp. 206–223.Google Scholar
  10. 10.
    A. V. Nikulina, V. A. Markelov, M. M. Peregud, et al., “Irirradiation-induced microstructural changes in Zr – 1% Sn – 1% Nb – 0.4% Fe,” J. Nucl. Mater., No. 238, 205–210 (1996).Google Scholar
  11. 11.
    V. N. Shishov, A. V. Nikulina, V. A. Markelov, et al., “Influence of neutron irradiation on dislocation structure and phase composition in Zr-base alloys,” in: Proc. 11th Int. Symp. on Zr in the Nuclear Industry, ASTM STP 1295 (1996), pp. 603–622.Google Scholar
  12. 12.
    A. V. Nikulina, V. N.Shishov, M. M.Peregud Irradiation induced growth and microstructure evolution of Zr –A. V. Nikulina, V. N. Shishov, M. M. Peregud, et al., “Irradiation induced growth and microstructure evolution of Zr –1.2Sn – 1Nb – 0.4Fe under neutron irradiation to high doses,” in: 18th Symp. on Effects of Radiation on Materials, ASTM STP 1325 (1997), pp. 785–804.Google Scholar
  13. 13.
    S. A. Averin, V. L. Panchenko, A. V. Kozlov, et al., “Evolution of dislocation and precipitate structure in Zr alloys under longtime irradiation,” in: 12th Int. Symp. on Zr in the Nuclear Industry (Toronto, Canada, dy1998), ASTM STP 1354 (2000), pp. 105–121.Google Scholar
  14. 14.
    V. N. Shishov, M. M. Peregud, A. V. Nikulina, et al., “Influence of zirconium alloy chemical composition on microstructure formation and irradiation induced growth,” in: 13th Int. Symp. on Zr in the Nuclear Industry (Annecy, France, 2000), ASTM STP 1423.Google Scholar
  15. 15.
    D. Gilbon, A. Soniak, S. Doriot, et al., “Irradiation creep and growth behavior and microstructural evolution of advanced Zr-base alloys,” in: 12th Int. Symp. on Zr in the Nuclear Industry (Toronto, Canada, 1998), ASTM STP 1354 (2000), pp. 51–73.Google Scholar
  16. 16.
    R. A. Holt, A. R. Causey, M. Griffiths et al, “High fluence irirradiation growth of cold-worked Zr – 2.5 Nb,” in: 12th Int. Symp. on Zr in the Nuclear Industry (Toronto, Canada, 1998), ASTM STP 1354 (2000), pp. 86–104.Google Scholar
  17. 17.
    M. Griffiths, R. W. Gilbert, et al., “Accelerated irirradiation growth of zirconium alloys,” in: 8th Int. Symp. on Zr in the Nuclear Industry, ASTM STP 1023 (1989), p. 658.Google Scholar
  18. 18.
    M. Griffiths, R. A. Holt, and A. Rogerson, “Microstructural aspects of accelerated deformation of Zircaloy nuclear reactor components during service,” J. Nucl. Mater., 225, 245 (1995).Google Scholar
  19. 19.
    M. Griffiths, J. F. Mecke, and J. E. Winegar, “Evolution of microstructure in zirconium alloys during irradiation,” in: 11th int. Symp. on Zr in the Nuclear Industry (Garmisch-Partenkirchen, Germany, 1995), ASTM STP 1295 (1996), pp. 580–602.Google Scholar
  20. 20.
    R. A. Holt, A. R. Causey, N. Christodoulou, et al., “Nonlinear irirradiation growth of cold worked Zircaloy-2,” in: 11th Int. Symp. on Zr in the Nuclear Industry, 1995, ASTM STP 1295 (1996), pp. 623–637.Google Scholar
  21. 21.
    V. I. Avramenko, Yu. V. Konobeev, and A. M. Strokova, “Neutron sections to calculate damage dose for reactor materials,” Atomn. Energiya, 56, Issue 3, 139–141 (1984).Google Scholar
  22. 22.
    R. B. Adamson, “Effect of neutron irradiation on microstructure and properties of Zircaloy,” in: 12th Int. Symp. on Zr in the Nuclear Industry (Toronto, Canada, 1998), ASTM STP 1354 (2000), pp. 15–31.Google Scholar
  23. 23.
    D. Gilbon and C. Simonot, “Effect of irradiation on the microstructure of Zircaloy-4,” in: 10th Int. Symp. on Zr in the Nuclear Industry, ASTM STP 1245 (1994), pp. 521–548.Google Scholar

Copyright information

© Plenum Publishing Corporation 2003

Authors and Affiliations

  • A. V. Nikulina
    • 1
  1. 1.A. A. Bochvar All-Russia Research Institute for Inorganic Materials (VNIINM)MoscowRussia

Personalised recommendations