Skip to main content
Log in

Zirconium-Niobium Alloys for Core Elements of Pressurized Water Reactors

  • Published:
Metal Science and Heat Treatment Aims and scope

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.

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.

Similar content being viewed by others

REFERENCES

  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. 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.

  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.

  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.

  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.

  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.

  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.

  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.

  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.

  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. 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.

  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.

  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.

  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.

  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.

  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.

  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.

  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. 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.

  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.

  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. 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.

  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.

Download references

Author information

Authors and Affiliations

Authors

Rights and permissions

Reprints and permissions

About this article

Cite this article

Nikulina, A.V. Zirconium-Niobium Alloys for Core Elements of Pressurized Water Reactors. Metal Science and Heat Treatment 45, 287–292 (2003). https://doi.org/10.1023/A:1027388503837

Download citation

  • Issue Date:

  • DOI: https://doi.org/10.1023/A:1027388503837

Keywords

Navigation