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On correlation of composition, structural-phase state, and properties of E635 zirconium alloy

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Inorganic Materials: Applied Research Aims and scope

Abstract

The results of research on the correlation of the alloying elemental content, structural-phase state, and properties prior to and after irradiation of the E635 zirconium alloy of the Zr-Nb-Sn-Fe system are generalized. The possibilities of controlling the viscosity, technological plasticity, and corrosion resistance through optimizing the content of the alloying elements and structural-phase state by virtue of development of deformation and thermal processing modes are shown. High resistance to radiation-induced deformation of the alloy results from the primary composition and the evolution of its structural-phase state under irradiation, in which iron plays a key role.

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References

  1. Zaimovskii, A.S., Nikulina, A.V., and Reshetnikov, N.G., Tsirkonievye splavy v atomnoi energetike (Zirconium Alloys in Nuclear Power Engineering), Moscow: Enegoizdat, 1981.

    Google Scholar 

  2. Ageenkova, L.E., Zaimovskii, A.S., and Nikulina, A.V., USSR Inventor’s Certificate no. 64815 USSR (SU 1751222Al). C 22 C 16/00, Bull. Izobret., 1992, no. 28.

  3. Nikulina, A.V., Markelov, P.P., Markelov, V.A., et al., RF Patent no. 2032759, 1995.

  4. Nikulina, A.V., Markelov, V.A., Gusev, A.Yu., et al., Zr-1% Sn-1% Nb-0.5% Fe Alloy for the Pipes of Technological Channels of High-Power Channel-Type Reactors, Vopr. Atomn. Nauki Tekhn. Ser. Atomn. Materialoved., 1990, issue 2 (36), pp. 58–66.

  5. Nikulina, A.V., Markelov, V.A., et al., Zirkonium Alloy E635 as a Material for Fuel Rod Cladding and Other Components of VVER and RBMK Cores, in Zirconium in Nuclear Industry: 11th Int. Symp. ASTM STP. 1295, 1996, pp. 785–804.

  6. Markelov, V., Novikov, V., Nikulina, A., et al., Application of E635 Alloy as a Structural Components of WWER-1000 Fuel Assemblies, Proc. 6th Int. Conf. WWER Fuel Performance. Modeling and Experimental Support, Albena, 2005, pp. 188–193.

  7. Shishov, V.N., Markelov, V.A., et al., Use and Improvement of E635 Alloy Applied to Fuel Claddings and FA Structural Components of Water Cooled Reactors, Proc. 6 Int. Symp. Contribution of Materials Investigation to Improve the Safety and Performance of LWRs, Fontevraud Royal. Abbey, Sept. 18–22, 2006, vol. 2, session B, pp. 969–981.

  8. Samoilov, O.B., The Results of Design, Exploitation and Development of Fuel Assembly of Alterative Structure for Water-Moderated Water-Cooled Power Reactor VVER-1000, Yadern. Toplivo AES. OAO “MSZ”, 2003, pp. 2–6.

  9. Markelov, V.A., Rafikov, V.Z., Nikulin, S.A., et al., The Way to Measure the Microstructure of Zirconium Alloy with Stanum, Niobium and Ferrum under Thermal-Deforming Treatment, Fiz. Met. Metalloved., 1994, vol. 77,issue 4, pp. 70–79.

    CAS  Google Scholar 

  10. Nikulin, S.A., Markelov, V.A., Goncharov, V.I., et al., Microstructure and Mechanical Properties Variation during Annealing of Zr-1.3% Sn-1% Nb-0.4% Fe Hardened Alloy, Izv. Akad. Nauk. Metally, 1995, no. 1, pp. 62–68.

  11. Markelov, V.A., Nikulina, A.V., Gusev, A.Yu., et al., Structure Variation Induced by Radiation in the Technological Channel Pipe Made of Zr-1.3 Sn-1 Nb-0.4 Fe Alloy under its Operation in the Reactor of Ignalina Nuclear Power Plant First Unit, Vopr. Atomn. Nauki Tekhn. Ser. Materialoved. Nov. Mat., 1993, issue 1 (48), pp. 44–49.

  12. Nikulina, A.V., Markelov, V.A., Peregud, M.M., et al., Irradiotiorbinduced Microstructure Changes in Zr-1% Sn-1% Nb-0.4% Fe, J. Nucl. Mater., 1996, no. 238, pp. 205–210.

  13. Shishov, V.N., Nikulina, A.V., Markelov, V.A., et al., Influence of Neutron Irradiation on Dislocation Structure and Phase Composition in Zr-Base Alloys, Zirconium in the Nuclear Industry: 11th Int. Symp. ASTM STP 1295, 1996, pp. 603–622.

  14. Shishov, V.N., Markelov, V.A., Nikulina, A.V., et al., Microstructure and Shape Variation of Zirconium Alloys, Vopr. Atomn. Nauki Tekhn. Ser. Materialoved. Nov. Mat., 2006, issue 1 (66), pp. 313–328.

  15. Fateev, B.M., Nikulin, S.A., Markelov, V.A., et al., The Estimation of Zirconium Alloys Technological Plasticity Obtained According to Tension Test Results, Vopr. Atomn. Nauki Tekhn. Ser. Materialoved. Nov. Mat., 1993, issue 1 (48), pp. 25–30.

  16. Nikulin, S.A., Goncharov, V.I., Markelov, V.A., and Shishov, V.N., Effects of Microstructure on Ductility and Fracture Resistance of Zr-1.3 Sn-1 Nb-0.4 Fe Alloy, Zirconium in the Nuclear Industry: 11th Int. Symp. ASTM STP 1295, 1996, pp. 685–709.

  17. Nikulin, S.A., Two Ways of Plastic Flow Stability Failure and Alloys Plasticity, Fiz. Met. Metalloved., 1996, vol. 81,issue 3, pp. 142–159.

    CAS  Google Scholar 

  18. Nikulin, S.A., Shtremel, M.A., and Markelov, V.A., Influence of Secondary Phase Particles of Zr-Alloys Plastic Flow Stability and Fracture, Proc. 1st European Mechanics of Materials Conf. on Local Approach to Fracture, Fontainebleau, 1996, pp. 133–143.

  19. Markelov, V.A., Nikulin, S.A., Gusev, A.Yu., et al., The Effect of Composition and Thermal-Deforming Treatment with β-Hardening to the Structure and Resistance Ability for Zirconium Alloy with Stanum, Niobium and Ferrum, Vopr. Atomn. Nauki Tekhn. Ser. Materialoved. Nov. Mat., 1993, issue 1 (48), pp. 37–43.

  20. Markelov, V.A., Nikulin, S.A., Gusev, A.Yu., et al., The Effect of Thermal-Mechanical Treatment Conditions onto the Structure and Properties of Zr-1.35 Sn-1 Nb-0.4 Fe Alloy, Vopr. Atomn. Nauki Tekhn. Ser. Materialoved. Nov. Mat., 1993, issue 1 (48), pp. 21–25.

  21. Markelov, V.A., Shishov, V.N., Zheltkovskaya, T.N., and Khokhunova, T.N., The Effect of Thermal-Deforming Parameters of Cold Rolling to the Structure, Mechanical Properties and Corrosion Resistance of E635 Alloy, in Sbornik dokladov IV mezhotraslevoi konf. po reaktornomu materialovedeniyu (Papers of IV Intersectorial Conf. on Material Science for Reactors), Dimitrovograd, 1995, vol. 2, pp. 27–38.

    Google Scholar 

  22. Markelov, V.A., Shishov, V.N., Zheltkovskaya, T.N., et al., The Effect of Chromium Additions to E635 Alloy Properties, in Sbornik dokladov V mezhotraslevoi konf. po reaktornomu materialovedeniyu (Papers of V Intersectorial Conf. on Material Science for Reactors), Dimitrovograd, 1997, vol. 2, part 1, pp. 245–253.

    Google Scholar 

  23. Markelov, V.A., Aktuganova, E.N., Zheltkovskaya, T.N., et al., The Effect of Texture and Structure-Phase State onto Fracture Toughness and Retarded Hydride Cracking of the High-Pressure Pipes Made of Zirconium Alloys, in Sbornik tezisov dokladov 2-i Evraziiskoi nauchno-prakticheskoi konf. “Prochnost’ neodnorodnykh struktur” (Papers of the Second Eurasian Scientific Conf. “Strength of Nonuniform Structures”), Moscow, 2004, p. 29.

  24. Markelov, V.A., Shishov, V.N., Kabanov, A.A., et al., The Ways to Increase the Technological Plasticity and Viscosity of E635 Alloy for the Units of Fuel Assembly of Water-Moderated Water-Cooled Power Reactor VVER-1000, Vopr. Atomn. Nauki Tekhn. Ser. Materialoved. Nov. Mat., 2009, issue 2 (75), pp. 119–131.

  25. Markelov, V.A., Novikov, V.V., Nikulina, A.V., et al., The State of Zirconium Alloys Development and Usage for Fuel Element and Fuel Assembly of the Active Zones of Nuclear Water-Cooled Reactors to Secure the Promising Fuel Cycles and Competitive Ability at the World Markets, Vopr. Atomn. Nauki Tekhn. Ser. Materialoved. Nov. Mat., 2006, issue 2 (67), pp. 63–72.

  26. Markelov, V.A., Novikov, V.V., Kon’kov, V.F., et al., Corrosion Behavior under Radiation of Zirconium Alloys of E110 and E635 Types for PWR Conditions, Vopr. Atomn. Nauki Tekhn. Ser. Materialoved. Nov. Mat., 2009, issue 2 (75), pp. 112–118.

  27. Novikov, V.V., Markelov, V.A., Tselishchev, A.V., et al., The Peculiarities of Structure-Phase Changes and Corrosion Behavior under Radiation of the Fuel Elements Shells Made of E110 and E635 Alloys in Water-Cooled Reactors, Vopr. Atomn. Nauki Tekhn. Ser. Materialoved. Nov. Mat., 2006, issue 1 (66), pp. 329–337.

  28. Garzarolli, F., Stchle, H., and Steinberg, E., Behavior and Properties of Zircaloys in Power Reactors: A Short Review of Pertinent Aspects in LWR Fuel, in Zirconium in the Nuclear Industry: Eleventh Intern. Symp. ASTM STP 1295, 1996, pp. 12–32.

  29. Adamson, R.B., Effect of Neutron Irradiation on Microstructure and Properties of Zircaloy, in Zirconium in the Nuclear Industry: Twelfth Intern. Symp. ASTM STP 1354, 2000, pp. 15–31.

  30. Foster, J.P., Yech, H.K., and Comstock, R.J., ZIRLOTM Cladding Improvement, in Zirconium in the Nuclear Industry: 15th Intern. Symp. ASTM STP 1505, 2009, pp. 457–470.

  31. Shivsov, V.N., Peregud, M.M., Nikulina, A.V., et al., Influence of Structure-Phase of Nb Containing Zr Alloys on Irradiation-Induced Growth, in Zirconium in the Nuclear Industry: Eleventh Intern. Symp. ASTM STP 1467, 2006, pp. 666–685.

  32. Holt, R.A., Mechanisms of Irradiation Growth of Alpha-Zirconium Alloys, J. Nucl. Mater., 1988, vol. 159, p. 310.

    Article  CAS  Google Scholar 

  33. Shishov, V.N., Peregud, M.M., Markelov, V.A., et al., Structure-Phase State, Corrosion and Irradiation Properties of Zr-Nb-Fe-Sn System Alloys, in Zirconium in the Nuclear Industry: 15th Intern. Symp. ASTM STP 1505, 2009, pp. 724–743.

  34. Smirnov, A., Markov, D., Smirnov, V., et al., Results of Post-Irradiation Examination of WWER Fuel Assembly Structural Components Made of E110 and E635 Alloys, Proc.6th Int. Conf. WWER Fuel Performance. Modeling and Experimental Support, Albena, 2005, p. 231–243.

  35. Wikmark, G., Hallstadius, L., and Yuen, K., Cladding to Sustain Corrosion, Creep and Growth at High Bunvup, 2008 Water Reactor Fuel Performance Meeting, Korea, 2008.

  36. Nikulina, A.V., Zirconium Alloys in Nuclear Industry, Materialoved. Termich. Obrab., 2004, no. 11, pp. 8–12.

  37. Nikulina, V.A., Shebaldov, P.V., Shishov, V.N., et al., RF Patent no. 2141540 RF, MPK 6 C 22 C 16/00, Byull. Izoret., 1999, no. 32.

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Correspondence to V. A. Markelov.

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Original Russian Text © V.A. Markelov, 2010, published in Materialovedenie, 2010, No. 2, pp. 41–49.

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Markelov, V.A. On correlation of composition, structural-phase state, and properties of E635 zirconium alloy. Inorg. Mater. Appl. Res. 1, 245–253 (2010). https://doi.org/10.1134/S2075113310030123

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